ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events
ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events
ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events
Create successful ePaper yourself
Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.
FINAL PROGRAM<br />
ICEM’11<br />
ICEM’11<br />
The 14th International Conference<br />
on Environmental Remediation and<br />
Radioactive Waste Management<br />
(ICEM)<br />
Date: September 25-29, 2011<br />
Location: Reims, France<br />
Reims Champagne Congrès (RCC) Centre<br />
ORGANIZED AND SPONSORED BY<br />
ASME Web site: www.asmeconferences.org/icem2011<br />
SFEN Web site: www.sfen.fr/icem-11<br />
Andra Disposal Facility<br />
Chooz Nuclear Power Plant
WELCOME TO ICEM’11<br />
The Fourteenth International Conference on Environmental Remediation and Radioactive Waste<br />
Management (ICEM’11) is a global information exchange, featuring engineering and scientific solutions to<br />
environmental problems. More than 600 scientists, engineers, managers, project directors, business<br />
representatives, equipment vendors and government officials from more than 30 countries are expected to attend<br />
the conference, held this year in Reims, France at the Reims Champagne Congrès (RCC) Centre.<br />
The Environmental Engineering (EED) and Nuclear Engineering Divisions (NED) of the American Society<br />
of Mechanical Engineers (ASME) have joined forces with the Société Française d’Energie Nucléaire (SFEN) for<br />
ICEM’11. The conference and exhibition will offer a unique opportunity to foster cooperation and establish<br />
contacts with participants from many countries. Conference participants will be able to speak directly with peers<br />
who are reporting new research, initiating and managing environmental projects, establishing national and<br />
international regulations and applying new methods and equipment. ICEM’11 is expected to feature 300<br />
technical papers, research presentations and discussions of field applications. A diverse group of international<br />
organizations will be exhibiting related technologies and services.<br />
We have organized this <strong>Final</strong> <strong>Program</strong> so you can easily find additional details on the technical program and<br />
ways to participate. Also included is a listing of Exhibitors, Sponsors and their services, and the technical<br />
abstracts. Please take a look inside for more details. We are sure you will find something of interest. We hope<br />
that you have a successful meeting and welcome to Reims!<br />
Conference General Co-Chairs<br />
Anibal Taboas, for ASME (USA)<br />
Dominique Greneche, for SFEN (FRANCE)<br />
Honorary Co-Chairs<br />
Mr. Christophe Behar, Nuclear Energy Director, CEA (FRANCE)<br />
Ms. Tracy Mustin, Principal Deputy Assistant Secretary for EM, DOE (USA)<br />
Mr. Francois-Michel Gonnot, Chairman of the Board, ANDRA (FRANCE)<br />
Dr. Tero Varjoranta, Director, Division of Nuclear Fuel Cycle and Waste Technology, IAEA (AUSTRIA)<br />
Mr. Arnaud Gay, Executive Vice President of the Nuclear Sites Value Development Business Unit,<br />
AREVA (FRANCE)<br />
Conference Managers<br />
Gary Benda, for ASME/ICEM (USA) and Bernard Jolly, SFEN (FRANCE)<br />
— EMERGENCY CONTACT INFORMATION —<br />
During the conference, in case of emergency, contact Tel : +33 (0)3 26 77 44 88.<br />
There will also be a guest message and program errata board located at the Registration Area, 1st Floor.<br />
We would like to thank the following companies for sponsoring<br />
the following events at the ICEM’11 Conference.<br />
~ Our Platinum Sponsors ~<br />
ANDRA — Tuesday Reception<br />
URS CORPORATION — Sunday Reception<br />
~ Our Gold Sponsor ~<br />
WESTINGHOUSE ELECTRIC COMPANY<br />
~ Our Silver Sponsor ~<br />
FLUOR CORPORATION<br />
~ Our Bronze Sponsors ~<br />
ATOMEXPO<br />
KRAFTANLAGEN HEIDELBERG GmbH<br />
ONET TECHNOLOGIES
Table of Contents<br />
ICEM’11 Corporate Sponsors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Inside Front Cover<br />
ICEM’11 Perspectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2<br />
Background, Location and Contact Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
Objectives and Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
Format and Venue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
City of Reims . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
Hotel - Accommodations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
Restaurants - Eating out in the City of Reims . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
Foreign Exchange and Traveler’s Cheques. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
Transportation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
Insurance and Liability . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
Disclaimer . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
ICEM’11 Organizing Societies and Cooperating Int'l Agencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
US Societies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
European Societies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
Cooperating International Agencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
Social <strong>Events</strong> and Guest <strong>Program</strong>s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
Sunday Golf Outing at Le Golf de Reims Champagne . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
Sunday Welcome Reception . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
Tuesday Reception . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
Wednesday Conference Banquet. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5<br />
Guest <strong>Program</strong>. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5<br />
Associated Technical <strong>Events</strong> . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6<br />
Technical Training Course . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6<br />
Technical Tours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6<br />
Major Topics and Panel Sessions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6<br />
Major Topics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6<br />
Participating Attendees . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6<br />
Monday Morning Opening Session . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7<br />
Poster Sessions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7<br />
Special Panel Sessions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7<br />
Conference Scheduling and Additional Information . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9<br />
Registration Hours. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9<br />
Exhibition Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9<br />
Coffee/Tea Breaks Information. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9<br />
Lunch Periods in Exhibit Halls Information. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9<br />
Daily Speaker/Session Co-Chair Briefing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9<br />
Presentation Times . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10<br />
Conference Proceedings on CD-ROM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10<br />
Audio Visual Office / Speaker Ready Area, Date and Time. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10<br />
Poster Sessions Setup Date and Time . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10<br />
Acronym List. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11<br />
Reims City Site Map . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12<br />
Reims Train Station to Reims Champagne Congres (RCC) Centre . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12<br />
Reims Road Map and Hotel Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13<br />
Reims Champagne Congres (RCC) Centre Maps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14-15<br />
Technical <strong>Program</strong> at a Glance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16-17<br />
Technical <strong>Program</strong> Descriptions - Sessions 1 - 60 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18-34<br />
Exhibit Hall Layout . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .38-39<br />
Exhibitor Descriptions and Sponsorship . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40-55<br />
Technical Abstracts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56-133<br />
Attendee Pre-registration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 133-142<br />
Technical <strong>Program</strong> Organizers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 143<br />
Session Organizers . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 143<br />
Conference Steering Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 144<br />
Schedule of <strong>Events</strong> . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Inside Back Cover<br />
1
2<br />
ICEM’11 PERSPECTIVES<br />
Thank you for being involved in the latest of the premier series of International Conferences on Environmental<br />
and Radioactive Waste Management sponsored by ASME International (ASME). The final<br />
ICEM’11 Conference <strong>Program</strong> should facilitate exchange of ideas to reduce risk, and avert the overwhelming<br />
costs of delay in resolving environmental and radioactive waste management issues.<br />
Meeting the high quality expectations of the event sponsors, the Societe Française d’Energie<br />
Nucléaire (SFEN) and ASME, requires enabling contribution of: sponsors and exhibitors; dedicated volunteer<br />
track and session chairs; and many others, from organizers to independent peer reviewers, and presen- Aníbal L. Taboas<br />
ters. As Conference General Co-Chairs we recognize the exceptional leadership of Gary Benda (Conference<br />
Manager) and Bernard Jolly (European Event Manager), whose intensive cooperation resulted in exceptional<br />
planning and execution.<br />
Our goal is to promote the necessary art, science & practice leading to sustainable global environmental<br />
management. This includes overarching discussion to complement the plenary session key-note presentations.<br />
Reims is specially fitting for its history as witness in evolution of the established world order.<br />
Challenges to contemporary global order include interdependent economic imbalance, regime change,<br />
zeal among newly-leading divergent populations, and reliance on electronic media as the primary source of Dominique Greneche<br />
information. Volatility diverts focus from topic concepts like concerted environmental action, to insular needs (such as the nearterm<br />
supply of food, water, and power, and security).<br />
Industrialized nations remain as unprepared to relocate populations in response to predicted sea level changes, as they are for<br />
the unprecedented strategic opportunity to transform the related supply and distribution of energy, food, commerce, and emerging<br />
populations. Similarly, while the risk of sovereign debt is recognized, there is scant movement to recognize the equally obligatory<br />
and non-discretionary nature of funding responsible environmental management. Ideological governance, however, continues<br />
unabated, and without apparent realization that maintaining the health of wealth generating engines, particularly manufacturing<br />
capability, is essential to sustainability.<br />
Transitory ideologies and obstructionists successfully inflate uncertainty and perceived technical risk with tricks such as<br />
reliance on non-rigorous or un-reproducible data, and extrapolation of performance expectations to absurd times. Projections that<br />
significantly deviate from defensible models, theory, and observation, necessarily decrease confidence on projected results. The<br />
misapplication of statistical methods, use of sloppy science, and the masterful use of mass communication tools, imparts plausibility<br />
to ideological biases, and masks competence and applicability limitations.<br />
Education imparts individual responsibility to ensure safety, advancement of technology, and to contribute to societal well-being.<br />
Scientists, engineers, technologists, and learned societies have a unique duty to engage in discourse of public policy. Effective communication<br />
is facilitated by simple and clear themes, such as: “Education, Energy, Environment, Economy, and National Security are<br />
inextricably intertwined”; “Society demands to be actively aware of details that influence their reasonable expectation of an adequate<br />
return on their investment in Governance”; and “Global partnerships are effective tools to demonstrate best-in-class performance.”<br />
Individuals frequently feel powerless to influence global outcomes, however, success continues to favor those who properly<br />
prepare to assess and manage risk. It is time for the technically educated to fulfill a responsibility for engagement at all levels of<br />
government on science and technology policies affecting the public interest.<br />
It is time to demand a return to basic principles, such as reliance on best available science, independent peer review; and<br />
increased intellectual honesty in regulatory engineering. It is time, for example, to get past regulation of waste disposal mechanisms<br />
according to the activity level and generating source, and to promulgate international guidelines to manage and dispose such waste<br />
exclusively on the basis of sound multi-media risk management. It’s time to initiate transition of international efforts away from<br />
insular engagement, and into supporting systematic approaches to inextricable factors.<br />
Our challenge is for you to find ICEM’11 as stimulating, cost effective, and constructive, as we intend it to be, and that you<br />
find it essential to join us for ICEM’13.<br />
Aníbal L. Taboas<br />
Dominique Greneche<br />
ICEM’11 Conference General Co-Chairs
Background, Location and<br />
Contact Information<br />
Objectives and Background<br />
The fourteenth International Conference on<br />
Environmental Remediation and Radioactive Waste<br />
Management (ICEM) promotes a broad global<br />
exchange of information on technologies, operations,<br />
management approaches, economics, and public<br />
policies in the critical areas of environmental<br />
remediation and radioactive waste management. The<br />
conference provides a unique opportunity to foster<br />
cooperation among specialists from countries with<br />
mature environmental management programs and those<br />
from countries with emerging programs. Attendees will<br />
include scientists, engineers, technology developers,<br />
equipment suppliers, government officials, utility<br />
representatives and owners of environmental problems.<br />
Format and Venue<br />
The ICEM’11 technical program includes concurrent<br />
technical sessions in five subject tracks:<br />
1. Low/Intermediate-Level Waste Management<br />
2. Spent Fuel, Fissile, Transuranic, High-Level Waste<br />
Management<br />
3. Facility Decontamination and Decommissioning<br />
4. Environmental Remediation<br />
5. Environmental Management / Public Involvement<br />
The technical program consists of an opening plenary<br />
session and several parallel program tracks with up to<br />
eight concurrent sessions. The sessions include 25<br />
minute oral presentations, panels, and poster displays<br />
which are designed to enhance dialogue between<br />
presenters and participants.<br />
The ICEM’11<strong>Program</strong> is divided into 60 technical<br />
sessions conducted over three and a half days.<br />
A listing of the specific sessions within each of the five<br />
technical program tracks can be found in the “Technical<br />
<strong>Program</strong> at a Glance” section. The full registration fee<br />
includes entrance to all technical presentations, the<br />
exhibit hall, the Sunday evening Welcome Reception,<br />
the Tuesday evening Exhibitor Reception, all<br />
refreshments during the conference breaks and lunch<br />
for three days. The meeting material provided includes<br />
the final program which includes the technical session<br />
abstract book, and a complete CD-ROM containing all<br />
approved papers that were presented, which will be<br />
mailed six months after the conference.<br />
City of Reims<br />
The city of Reims is fairly small and easily walkable,<br />
with many streets for pedestrians only. Reims, the home<br />
of champagne (the most celebrated and celebrating<br />
wine in the world), is the main city of the champagne<br />
area. It is a charming city, and one that the French hold<br />
dear to their hearts.<br />
In Reims stands one of the most beautiful buildings of<br />
the Middle Ages in Europe, one that is filled with<br />
history:<br />
Notre-Dame de Reims. The baptism of Clovis, around<br />
the year 498, gave birth to the Kingdom of the Franks,<br />
where the cathedral now stands. In 816 at the cathedral<br />
took place the first royal coronation in Reims, the one<br />
of Louis le Pious. This exceptional event explains the<br />
choice of Reims as the coronation city. Almost all<br />
French kings were crowned there for about 1,000 years.<br />
Reims, and surrounding Epernay and Ay are the main<br />
places of champagne production. Many of the largest<br />
champagne producing houses, referred to as les grandes<br />
marques, have their head office in Reims. Most are<br />
open for champagne tasting and tours by appointment<br />
only. The champagne is aged in the many chalk caves<br />
and tunnels, some originating in the Roman period,<br />
located deep inside the ground.<br />
Hotel - Accommodations<br />
ICEM has teamed with the Reims Tourism Board to<br />
assist in room accommodations. Participants that made<br />
arrangement through them, can reach them for any<br />
reason. Contact: Reims Tourism Board, 12 bd du<br />
Général Leclerc - 51722 REIMS cedex, Telephone:<br />
03 26 77 44 74, Website: www.reims-evenements.fr.<br />
The ICEM’11 Committee is not responsible for any<br />
violations of any ordinances, and all other claims of<br />
losses, costs, and damages arising from the attendee’s<br />
occupancy at any of the local hotels.<br />
Restaurants - Eating out in Reims City Region<br />
During the day, delegates can enjoy the numerous bars<br />
and restaurants down the avenue from the conference<br />
centre. During the night, come celebrate with us and<br />
indulge in Reim’s best restaurants, cafes and bars. The<br />
area continues to astound with new and ever evolving<br />
imaginative food offerings which highlight the fantastic<br />
diversity this city has to offer. If you cannot decide<br />
where to eat check out http://www.reims-tourism.com/<br />
which can guide you to some of the best places in the<br />
area.<br />
Foreign Exchange and Traveler’s Cheques<br />
The conference secretary on-site will accept only<br />
EUROs (no US$ or Traveler's Cheques) for payment of<br />
any registration or optional ticket fees. Visa, American<br />
Express, and MasterCard are also accepted.<br />
Transportation<br />
Transportation by Air to Reims, France<br />
The Paris Charles De Gaulle (CDG) International<br />
Airport provides direct access to and from major<br />
European and North American cities and is a 50 minute<br />
drive from Reims. Reims is also located 30 mins. from<br />
the Paris Roissy international airport. Several<br />
companies also offer connections to these airports.<br />
Reims-Prunay aerodrome: Light business and tourist<br />
aircraft or Phone: +33 (0)3 26 49 10 92<br />
Transportation by Rail to Reims<br />
The easiest way to get to Reims from the CDG airport<br />
is by train. Reims is located at the junction of the Lille -<br />
Dijon - Mediterranean and Paris - Charleville – Sedan<br />
lines with 12 daily links between Reims-Paris. A TGV<br />
high-speed train links Reims to Paris in 45 mins.<br />
Travelers coming from Lille or Paris CDG airport<br />
arrive at Champagne Ardenne TGV station, around 3<br />
miles (5km) outside Reims. Regular local train services<br />
connect this station to Reims city station. To consult the<br />
times and reserve your ticket:<br />
http://www.sncf.com/en_EN/html/ or<br />
www.tgvesteuropeen.com.<br />
3
4<br />
Transportation by Car to Reims<br />
Reims is located at the crossroads of the A4-E50 (Paris<br />
- Strasbourg) and A26-E17 (Calais - Troyes - Dijon)<br />
motorways. The city has 6 motorway exits. To<br />
determine a specific route visit: www.viamichelin.com<br />
Insurance and Liability<br />
All participants are encouraged to make their own<br />
arrangements for health and travel insurance. Neither<br />
ASME, Société Française d’Energie Nucléaire (SFEN)<br />
nor their agents, can be held responsible for any<br />
personal injury, loss, damage, accident to private<br />
property or additional expenses incurred because of<br />
delays or changes in air, rail, sea, road or other services,<br />
strikes, sickness, weather or any other cause.<br />
Disclaimer<br />
Neither ASME or Société Française d’Energie Nucléaire<br />
(SFEN) can accept any liability for death, injury, or any<br />
loss, cost or expense suffered or incurred by any person<br />
if such loss is caused or results from the act, default or<br />
omission of any person other than an employee or agent<br />
of ASME or Société Française d’Energie Nucléaire<br />
(SFEN). In particular, neither ASME nor Société<br />
Française d’Energie Nucléaire (SFEN) can accept any<br />
liability for losses arising from the provision or nonprovision<br />
of services provided by hotel companies or<br />
transport operators. Nor can ASME or Société Française<br />
d’Energie Nucléaire (SFEN) accept liability for losses<br />
suffered by reason of war including threat of war, riot<br />
and civil strife, terrorist activity, natural disaster,<br />
weather, flood, drought, technical, mechanical or<br />
electrical breakdown within any premises visited by<br />
delegates and/or partners in connection with the<br />
conference, industrial disputes, governmental action,<br />
regulations or technical problems which may affect the<br />
services provided in connection with the conference.<br />
Neither ASME nor Société Française d’Energie<br />
Nucléaire (SFEN) is able to give any warranty that a<br />
particular person will appear as a speaker or panelist.<br />
ICEM’11 Organizing Societies and<br />
Cooperating International Agencies<br />
U.S. Societies<br />
The Environmental Engineering Division (EED) and<br />
the Nuclear Engineering Division (NED) of ASME are<br />
the primary organizing societies of the ICEM<br />
conference. Since its inception in 1987, the objective<br />
has been to conduct international conferences on key<br />
environmental management topics in locations<br />
convenient to large numbers of technical experts from<br />
emerging environmental programs. ASME is committed<br />
to continue to provide this global conference wherever<br />
the greatest need and interest are shown.<br />
ICEM’11 is also organized to support the US<br />
Department of Energy (US DOE), the US Nuclear<br />
Regulatory Commission (US NRC) and the US<br />
Environmental Protection Agency (US EPA) along with<br />
several other major international technical societies and<br />
governmental organizations. Each agency has had<br />
significant involvement with the ICEM series. The US<br />
DOE is responsible for managing the wastes and<br />
cleaning the sites from the past US government nuclear<br />
operations, thus the US DOE staff has viewed this<br />
conference series as an opportunity to identify new<br />
technical solutions and to provide information on the<br />
results of their programs to the international<br />
community. Federal regulatory participants from both<br />
the US EPA and US NRC have also been active in<br />
program development and participation.<br />
European Societies<br />
The ICEM conferences have always been conducted<br />
jointly with a major local technical society and other<br />
co-societies in the host country. For ICEM’11, the<br />
Société Française d’Energie Nucléaire (SFEN) will help<br />
partner in the organization of this conference along with<br />
OECD (Organisation for Economic Co-operation and<br />
Development) and the Nuclear Energy Agency.<br />
Cooperating International Agencies<br />
Since the beginning, the ICEM meetings have been<br />
held in cooperation with major international<br />
organizations responsible for programs and research in<br />
radioactive waste management and environmental<br />
remediation fields. The International Atomic Energy<br />
Agency (IAEA) has been assisting this conferencein<br />
several ways. Their support has included assistance in<br />
the technical program preparation, presentation of<br />
technical papers and other agency information,<br />
promotion of the conference to their member states, and<br />
providing financial and technical assistance.<br />
Social <strong>Events</strong> and Guest <strong>Program</strong><br />
The conference registration fee includes lunch for three<br />
days (Monday to Wednesday), the Sunday Welcome<br />
Reception sponsored by URS and the Tuesday<br />
Reception sponsored by Andra. Tickets for the<br />
Conference Banquet on Wednesday are optional and are<br />
charged at a nominal price. Please note space is limited<br />
and tickets will be issued on a first-come first-served<br />
basis in EURO currency only.<br />
Sunday Golf Outing at Le Golf de Reims Champagne<br />
Golf de Reims Champagne is an international golf<br />
course to the extent of professional and amateur<br />
champions, open every day of the year. The course is<br />
located in a sleepy village just under 10 minutes from<br />
Reims. A group of attendees will meet and golf together<br />
before the conference starts. Additional information can<br />
be found at http://www.golf-dereims.com/diaporama.html<br />
or by contacting Virgene<br />
Mulligan, vmulligan@amrad.com.<br />
Sunday Welcome Reception – Sponsored by URS,<br />
Platinum Sponsor<br />
All conference participants are invited to attend the<br />
Welcome Reception on Sunday from 6:00pm to 8:00pm<br />
at the RCC located by the registration area on the<br />
second floor (“Le Bouchon” Space). Attendance is<br />
included in the conference registration fee. Delegate<br />
badges are required to gain entry and will be available<br />
at the registration desk between 4:00pm - 7:00pm.<br />
Guests are welcome but will be required to purchase a<br />
ticket for EURO €27 plus VAT.<br />
Tuesday Reception – Sponsored by Andra, Platinum<br />
Sponsor<br />
In order to celebrate Andra's 20th Anniversary, Ms.<br />
Marie-Claude Dupuis, Chief Executive Officer is pleased<br />
to invite all of the participants of ICEM 2011 to a buffet<br />
on Tuesday evening, 27 September 2011. This reception<br />
is sponsored by Andra for all registrants and will be held<br />
from 6:00pm to 8:00pm in the Exhibit Hall. Delegate
adges are required to gain entry and guests are welcome<br />
but will be required to purchase a ticket for EURO €27<br />
plus VAT at the registration desk prior to this event.<br />
Please take this opportunity to review, evaluate and test<br />
the current products and services of the exhibiting<br />
companies. They look forward to seeing everyone there<br />
to celebrate this anniversary.<br />
Wednesday Conference Banquet<br />
The entertainment hallmark of the ICEM conference is<br />
the traditional and culturally festive banquet, reflective<br />
of the host country. This year’s ICEM 2011 Banquet<br />
will be held at the Champagne De Castelnau Caveau<br />
from 7:30pm to 11:30pm. A four course meal with four<br />
different champagnes will be served. The ICEM<br />
Conference Banquet is an optional extra, but truly<br />
memorable. Tickets and badges will be required to gain<br />
entrance. Please note: This event is not included in the<br />
purchase price of your registration fee, there is an<br />
additional nominal cost to attend this event. Guests are<br />
also welcome to attend this event. For our fully paid<br />
conference registrants: EURO €54 plus VAT and for our<br />
Guests: €67 plus VAT.<br />
Guest <strong>Program</strong><br />
ICEM will sponsor a Guest Welcome Reception, hosted<br />
by Ms. Dianne Benda on Monday morning at 8:00am in<br />
Room 1 on Level 2. This “Guest Welcome Reception”<br />
will review all of our scheduled tour options available.<br />
While there will be tourism information available<br />
throughout the event, we encourage you to attend to<br />
answer questions and assist you in planning your week<br />
in Reims and its surrounding areas to make the most of<br />
your visit.<br />
You must arrive at least a half hour prior to the<br />
scheduled departure time of that scheduled tour. All<br />
Tours unless otherwise noted are accompanied by an<br />
English Speaking guide and will depart from and return<br />
to the RCC, registration area on the 1st floor. Upon<br />
availability, last minute tickets can be purchased. Only<br />
EURO currency will be accepted.<br />
Day Tour to Paris (Guided Tour #1)<br />
Sunday, 25th September, 9:00am-5:-00pm,<br />
135 € + VAT<br />
On Sunday, we are organizing a group to travel by train<br />
from Reims to Paris and enjoy a brief time in the local<br />
area. At the Paris East train station, we will board a Hop<br />
On – Hop Off bus for a 4 hour quick city tour. We will<br />
hop off at Notre Dame, The Eiffel Tower and at the<br />
Place d’Concorde and you will be able to have lunch on<br />
one of the stops on your own. After our tour of the<br />
highlights of Paris we will re-board the train at 4:00pm<br />
in time to return to the RCC for the Sunday reception.<br />
Cost includes roundtrip train, escort and tour bus. The<br />
group will meet on Sunday at the Best Western Hotel at<br />
8:15am and later at the Reims Train Station at 8:45am.<br />
Walking Tour of Reims (Guided Tour #2A)<br />
Monday, 26th September, 9:00am – 12:00pm,<br />
25 € + VAT<br />
(Note: This tour is also available on Thursday, 2:15 –<br />
6:00 as Guided Tour #5)<br />
Circus School, Paris and Mars Gates, Forum and<br />
Royal Square, Notre Dame with Guide. Sights<br />
include;<br />
• Hard Built Circus and Riding School - 19th<br />
century, now renovated and used for shows<br />
• The Paris Gate - built for the coronation of Louis<br />
XVI in 1775<br />
• The Gate of Mars - one of the four arches built ca.<br />
200 AD to mark the four main thoroughfares of<br />
Durocortorum, capital of the Roman province of<br />
Belgica.<br />
• The City Hall - typical of 17th century<br />
architecture. The facade bears an equestrian statue<br />
of King Louis XIII in its centre<br />
• The Forum Square - located on the site of the<br />
antique forum, this square was the market place,<br />
Gallo-roman Cryptoporticus (semi-subterranean<br />
gallery) and the Le Vergeur House Museum,<br />
• The Royale Square - ca. 1760, the square was<br />
built by the population as a tribute to Louis XV. In<br />
its centre, stands a statue of the king surrounded by<br />
a series of symbolic decorative figures by Pigalle.<br />
• The Notre-Dame Cathedral - a master-piece of<br />
gothic art, the Cathedral of Our Lady was started in<br />
1211. It was the Cathedral of the Coronations for<br />
French Kings in memory of the baptism of Clovis<br />
by Saint Remi on Christmas Day 498.<br />
Walking Tour of Reims / Champagne Cellars Tour<br />
(Guided Tour #2B)<br />
Monday, 26th September, 2:15pm – 6:00 pm,<br />
43 € + VAT<br />
The Basilica St-Remi and Champagne Cellars Taittinger,<br />
with Guide. Sights include;<br />
• Basilica Saint-Remi - The largest Romanesque<br />
pilgrimage church in northern France. It was built<br />
as a shrine to Saint Remi. The nave was<br />
consecrated in 1049 whereas the apse was built in<br />
the late 12th century.<br />
• Visit of Champagne Cellars – Taittinger -<br />
Located in the heart of Reims, between City Hall<br />
and the Cathedral, the Demeure des Comtes de<br />
Champagne makes the historical heritage of the<br />
city. Built in the 13th century, and partially<br />
destroyed during the First World War, it was<br />
restored under the direction of the Fine Arts<br />
Ministry. The tour will be concluded by a<br />
Champagne tasting. Price includes entrance fee to<br />
the champagne house.<br />
Visit of the Champagne Vineyard by Coach with<br />
Lunch (Guided Tour #3)<br />
Tuesday, 27th September, 9:30am – 5:00pm,<br />
97 € + VAT<br />
Cruise near Epernay on the Marne River.<br />
• Travel through the Champagne Vineyards - For<br />
the past three centuries, the passion of the men of<br />
Champagne and their respect for local traditions<br />
have resulted in the exceptional wines that are<br />
famous around the world for their subtle and<br />
delicate bouquet.<br />
• Meeting at Cumieres for Lunch Cruise - The<br />
jetty is located in the small village of Cumieres,<br />
near Epernay. You will sail on a sternwheeler<br />
between the vineyard covered slopes and the viticol<br />
villages nested on hillsides. After the lock, different<br />
species of birds will escort you to the doors of the<br />
Valley of the River Marne. All the history of the<br />
region seems to spring at each turn of the river: the<br />
castle of the famous Veuve Clicquot, Dom<br />
Perignon, the revolt of the wine-growers in 1911,<br />
the Duchess of Uzes, and so on.<br />
5
6<br />
• End Of The Cruise And Travel To Hautvillers<br />
Village - On the outskirts of Epernay, a small<br />
village known around the world thanks to a<br />
Benedictine monk named Dom Perignon, is<br />
perched on sunny vine planted hillsides. The<br />
legend of Dom Perignon adds an intangible but no<br />
less genuine aura to Hautvillers. He is said to have<br />
been able to make a “grey” or red still Champagne<br />
wine into a sparkling wine of perfect clarity. Dom<br />
Perignon is buried in the village church. The tour<br />
will include a champagne toasting.<br />
The Old City of Troyes and Shopping Outlet by<br />
Coach (Guided Tour #4)<br />
Wednesday, 28th September, 9:00am -5:30pm,<br />
85 € + VAT<br />
• Troyes - Travel by bus to see the Champagne Fairs<br />
and the Saint-Jean-au- Marche quarter. It is mainly<br />
in the urban fabric that the memory of the great<br />
Champagne Fairs can be found, fairs that were held<br />
in the city of Troyes during the festival of Saint<br />
Vincent and Saint Remi. The confusion of streets<br />
and small squares with closed courtyards give an<br />
idea of the city at this period.<br />
• Cathedral of Saint Peter and Saint Paul - This<br />
cathedral was built between the 13th and 15th<br />
centuries and is characteristic of the Gothic style.<br />
Only the Saint Peter tower was completed - the<br />
Saint Paul tower has remained unfinished since<br />
1545.<br />
• The Saint-Pantaleon Church, the Parish of the<br />
Polish Community of Troyes - Built on the site of<br />
a synagogue (according to tradition), a genuine<br />
museum of 16th century Troyes statuary, since it<br />
was the hiding place for statues saved during the<br />
French Revolution. Some were created by<br />
Dominique le Florentin, an artist from Troyes and<br />
decorator for Francois 1st.<br />
• Shopping - Factory and Trade Outlets - Troyes<br />
Designer Outlet - The first of McArthurGlen’s<br />
discount outlet malls in France, having opened in<br />
1995. It’s not surprising that McArthurGlen chose<br />
this city as the location for their designer outlet as<br />
Troyes’ association with textile manufacture and<br />
knitting go back to the 12th century. The Marque<br />
Avenue and Marques City outlets will also be<br />
visited. Here you’ll find 210 top fashion names.<br />
Walking Tour of Reims / Champagne Cellars Tour<br />
(Guided Tour #5)<br />
Thursday, 29th September, 2:15pm – 6:00pm,<br />
43 € + VAT<br />
The Basilica St-Remi and Champagne Cellars Taittinger<br />
with Guide. This is the same tour as Monday afternoon<br />
Tour #2B, but provides the attendee in sessions all week<br />
a second opportunity to see and taste at little of Reims<br />
and the Champagne region.<br />
Associated Technical <strong>Events</strong><br />
Technical Training Course<br />
RISK REDUCTION IN REMEDIATION, WASTE<br />
MANAGEMENT AND DECOMMISSIONING<br />
Sunday: 9:00am-4:00pm Room: 5<br />
The workshop is being held as a service to the ICEM<br />
community and is relevant to all technical program<br />
attendees as well as other professionals in the nuclear<br />
field. This workshop is intended as a condensed but<br />
intense training in the subject area of risk reduction for<br />
nuclear remediation, radioactive waste management and<br />
decommissioning of nuclear reactors and facilities.<br />
Participants will receive a certificate of training<br />
completion. Professional education credits may be<br />
available from ASME, IHMM or other organizations.<br />
Topics covered will include risk assessment, risk<br />
reduction methodologies, risk vs. cost, and practical<br />
lessons from various projects. Technical experts from<br />
the industry and senior leaders from international<br />
organizations will be invited as lecturers. The workshop<br />
will be directed by Dr. Jas Devgun.<br />
The agenda consists of six hours of intense instruction<br />
with a one hour lunch break. Refreshments for coffee<br />
breaks will be provided.<br />
Technical Tours<br />
Three technical tours are planned to see Andra and<br />
Chooz D&D project radioactive waste management<br />
programs first hand. The tours will take place<br />
immediately after the conference on Friday. Please<br />
Note: Tours will depart on Friday at 7:00 am at the<br />
RCC centre.<br />
1. Reims to Andra, LLW Site Tour (Tour 1A)<br />
• The Disposal Facilty for Low-Level and<br />
Intermediate-Level (LIL) Waste<br />
• The Disposal Facility for Very-Low-Level (VLL)<br />
Waste<br />
2. Reims to Andra, HLW Site Tour (Tour 1B)<br />
• The Underground Laboratory<br />
• Saudron' s Technological Centre<br />
3. Reims to Chooz, D&D Technical Tour (Tour B)<br />
Major Topics and Panel Session<br />
Major Topics<br />
The <strong>ICEM11</strong> Technical <strong>Program</strong> is divided into 60<br />
technical sessions conducted over three and one-half<br />
days. A listing of the specific sessions within each of<br />
the five technical programs can be found in the<br />
“<strong>Program</strong> at a Glance” Section.<br />
Participating Attendees<br />
Over 400 abstracts have been accepted from more than<br />
30 countries, including submittals from Western<br />
Europe, Central and Eastern Europe, the Far and<br />
Middle East, North and South America and Australia.<br />
This strong technical program is expected to draw more<br />
than 600 scientists, engineers, managers, project<br />
directors, utility and other business representatives,<br />
equipment vendors and government officials from<br />
around the world.<br />
The traditionally strong participation from countries<br />
with mature environmental programs will be<br />
supplemented by a contingent of attendees from Central<br />
and Eastern Europe, as well as key representatives from<br />
other countries from around the world with emerging<br />
programs. In the past, the ICEM meetings have allowed<br />
participants to exchange technical information, discover<br />
solutions to problems and make valuable business<br />
contacts or even arrange business agreements.
Monday Morning Opening Session<br />
SESSION 1 - PLENARY - OPENING SESSION<br />
Monday: 9:00am -12:30pm Room: Salle Royale<br />
The Opening Session will begin Monday morning with<br />
the keynote presentations setting the theme for this<br />
year’s conference. Coffee will be served on the 2nd<br />
floor Foyer from 08:00 until the program begins at<br />
9:00am.<br />
A break is scheduled after the third speaker.<br />
The Welcome speakers and Keynote speakers are:<br />
• Mr. Christophe Behar, Nuclear Energy Director,<br />
CEA (France)<br />
• Ms. Tracy Mustin, Principal Deputy Assistant<br />
Secretary for EM, DOE (USA)<br />
• Mr. Francois-Michel Gonnot, Chairman of the<br />
Board, Andra (France)<br />
• Dr. Tero Varjoranta, Director, Division of<br />
Nuclear Fuel Cycle and Waste Technology, IAEA<br />
(Austria)<br />
• Mr. Arnaud Gay, Executive Vice President of the<br />
Nuclear Sites Value Development Business Unit,<br />
AREVA (France)<br />
Special Panel Sessions<br />
Listed below is a brief summary on the ICEM2011<br />
panels. A more comprehensive and detailed description<br />
and the panelists are listed in the Technical <strong>Program</strong><br />
section with each Session.<br />
Poster Sessions<br />
The conference technical program will contain three<br />
major Poster Sessions on Monday - Wednesday<br />
arranged from the five Technical Tracks. The leading<br />
objective for the poster sessions is to provide a forum<br />
for experts in the field and interested attendees to gather<br />
in the RCC where they can move around freely and<br />
engage in discussions, which would normally not be<br />
possible during the oral sessions. The three best Posters<br />
from each Track will be displayed on Thursday<br />
morning.<br />
SESSION 2: APPROACHES FOR<br />
INTERNATIONAL COLLABORATION (5.18)<br />
Monday: 1:45pm - 6:00pm Room: 1<br />
An important element to reducing the cost and schedule<br />
of a country’s and/or organization’s environmental<br />
remediation mission is forming key international<br />
collaborative partnerships that focus on identifying and<br />
leveraging international expertise, infrastructure, and<br />
collaboration opportunities. This panel will provide an<br />
overview of the different approaches and initiatives<br />
used to promote international collaboration in<br />
environmental remediation and/or radioactive waste<br />
management, with a focus on the challenges and<br />
opportunities unique to each country and/or<br />
organization.<br />
Panelists Include: Mark Butez, Andra (France);<br />
John Mathieson, NDA (UK); Ian Bainbridge, AECL<br />
(Canada); Jong-Kil Park, KHNP (Korea);<br />
Malgorzata K. Sneve, Norwegian Radiation Protection<br />
Authority (Norway)<br />
SESSION 3: LESSONS LEARNED: FUKUSHIMA,<br />
CHERNOBYL-25 YEARS LATER, TMI-2 &<br />
OTHER EXPERIENCES (3.11)<br />
Monday: 1:45pm - 6:00pm Room: Salle Royale<br />
This panel was initially planned to discuss confinement<br />
activities and lessons learned from Chernobyl at a time<br />
of 25th anniversary of the Chernobyl accident (April<br />
26, 1986), lessons from TMI-2 accident (March 28,<br />
1979) and other industry experience with smaller<br />
events. However, the natural events of March 11, 2011<br />
(large earthquake and tsunami) led to the accident at the<br />
Fukushima- Dai-ichi complex which has been given the<br />
highest rating of seven on the international scale,<br />
equivalent to that of the 1986 Chernobyl crisis. The<br />
recovery efforts at Fukushima are still ongoing. This<br />
panel will discuss lessons learned from Fukushima,<br />
Chernobyl, and TMI-2 related to recovery, confinement,<br />
decommissioning, and future design lessons.<br />
Panelists Include: Dr. Tero Varjoranta, IAEA<br />
(Austria); Sergii Mitichkin, Chernobyl NPP (Ukraine);<br />
Thomas Chauveau, Bouygues-Construction (France);<br />
Didier Dall’ava, CEA/DEN/DADN (France);<br />
Svetlana Bratskaya, Institute of Chemistry of Russian<br />
Academy of Science (Russia); Dominique Greneche,<br />
SFEN (France); and Claudio Pescatore, OECD/NEA<br />
(France)<br />
SESSION 10: EMERGING ISSUES IN THE<br />
MANAGEMENT OF I/ILW (1.16)<br />
Tuesday: 8:30am - 12:30pm Room: 1<br />
This panel will focus on strategies for the management<br />
of all low and intermediate level waste (L/ILW). Based<br />
on experience in different national programs, it will<br />
discuss various options and their merits for managing<br />
L/ILW. It will consider the definition of different<br />
categories of L/ILW and their potential routes for<br />
disposal including waste of very low activity, often<br />
arising in high volumes as contaminated land, or from<br />
decommissioning. There will be discussion on large,<br />
disused components that are part of the<br />
decommissioning L/ILW waste stream. The<br />
engineering of facilities for the disposal of all such<br />
wastes should be proportionate to the long-term<br />
environmental impact that might arise.<br />
Panelists Include: Irena Mele, Section Head of Waste<br />
Technology, IAEA (Austria); Keith McConnell,<br />
Deputy Director, US NRC (USA); Bruno Cahen,<br />
Director, Andra (France); Geraldine Dandrieux, Head<br />
of Waste, Research Facilities and Fuel Cycle Facilities<br />
Department (France); Kazuyuki Kato, Federation of<br />
Electric Power Companies (Japan); Paul Dixon, Los<br />
Alamos National Lab (USA); and Dick Raaz, Chairman<br />
and Director, UK LLWR (UK)<br />
SESSION 11: HOW CAN NETWORKS IMPROVE<br />
THE IMPLEMENTATION OF ER PROJECTS?<br />
THE IAEA NETWORK ON ENVIRONMENTAL<br />
MANAGEMENT AND REMEDIATION-<br />
ENVIRONET (4.15)<br />
Tuesday: 8:30am-12:30pm Room: 4<br />
Environmental remediation projects tend to be<br />
constrained by several aspects being the lack of<br />
financial resources one of the most prominent factors.<br />
However, even when financial resources are available<br />
lack of institutional framework (e.g. lack of<br />
regulations), lack of human resources, and absence of a<br />
solid technical basis at the national level will contribute<br />
to slow the pace of implementation. Networking intends<br />
to bring problem holders and solution donors together<br />
7
8<br />
and enhance the exchange of experience while fostering<br />
the construction of partnerships. The ENVIRONET was<br />
initially presented to the international community at<br />
WM 2010. The ICEM 2011 will be an opportunity to<br />
present its achievement, broaden its affiliation and build<br />
an agenda of activities for the next years.<br />
Panelists Include: Leo van Velzen, NRD<br />
(Netherlands); Peter Booth, WSP Group (UK); and<br />
joining after the break - Irena Mele, Section Head of<br />
Waste Technology, IAEA (Austria)<br />
SESSION 20: CHALLENGES WHEN SELECTING<br />
DISPOSAL OPTIONS IN THE LIGHT OF THE<br />
NEW IAEA CLASSIFICATION SCHEME (1.17)<br />
Tuesday: 1:45pm - 6:00pm Room: 1<br />
The new IAEA classification scheme is based on long<br />
term safety – primarily disposal. The potential options<br />
for disposal include: above surface engineered landfill,<br />
near surface disposal (trenches, vaults or shallow<br />
boreholes), engineered facilities at intermediate depth<br />
(10s to 100s of meters) and geological disposal (> few<br />
hundred metres). Specific waste types will need specific<br />
consideration (e.g. disused sealed sources, graphite<br />
waste, and radium bearing waste). National schemes<br />
will be circumstance dependent.<br />
The following will be discussed:<br />
• Near surface or geological disposal for SL-LILW<br />
• Separate disposal for SL-LILW and VLLW<br />
• Advantages and disadvantages of opting for codisposal<br />
• Borehole disposal as potential solution for the<br />
countries having limited waste inventories<br />
• Feasible approaches for disposal of low level longlived<br />
waste<br />
This panel will provide a forum for the exchange of<br />
scientific and technical information on disposal of<br />
different categories of radioactive waste with focus on<br />
current approaches.<br />
Panelists Include: Linde Nel, Director of Operations<br />
and Maintenance Services (South Africa); Vaclav<br />
Hanusik, Senior Researcher, VUJE (Slovak Republic);<br />
Dr. Irina Gaus, Senior Expert (Switzerland); Thibaud<br />
Labalette, <strong>Program</strong> Director at Andra (France); Balint<br />
Nos, Head of Strategy Development and Engineering<br />
Office of PURAM (Hungary); Dr. Peter Brennecke,<br />
Bundestamt fur Strahlenschutz (BFS), Retired<br />
(Germany); Dr. Kazumi Kitayama, Senior Technical<br />
Advisor, Nuclear Waste Management Organization of<br />
Japan (NUMO) (Japan); and Keith McConnell,<br />
Deputy Director, US NRC (USA)<br />
SESSION 21 & 22: CONTRIBUTION AND<br />
COMPLEMENTARITIES OF INTERIM<br />
STORAGE, GEOLOGICAL DISPOSAL,<br />
PARTITIONING & TRANSMUTATION<br />
REVERSIBILITY REGARDING GLOBAL<br />
OPTIMIZATION OF RADWASTE<br />
MANAGEMENT (2.15)<br />
Tuesday: 1:45pm-3:30pm Room: 4<br />
Tuesday: 4:15pm-6:00pm Room: 4<br />
Session 21 is a two part panel in conjunction with<br />
Session 22. The first part will consist of a introductory<br />
paper and then a panel will address the status of HLW<br />
and Spent Fuel interim storage, processing and national<br />
programs. Partitioning and transmutation are also<br />
investigated in several countries. Interim storage is<br />
required to accommodate waste as long as sustainable<br />
management solutions are not available and interim<br />
storage duration up to 100 years has been often<br />
considered.<br />
Speakers Include: Bernard Boullis, CEA (France);<br />
Wilhelm Bollingerfehr, DBE (Germany); Philippe<br />
Lallieux ONDRAF (Belgium); Claudio Pescatore,<br />
NEA, (France); Jean-Michel Hoorelbeke, Andra<br />
(France); Farok Sharif, URS (USA); Jürg Schneider,<br />
NAGRA (Switzerland); and Neil Smart, NDA (UK)<br />
SESSION 29: INTERNATIONAL<br />
COOPERATION: NEA ROAD MAP, HOW TO<br />
INCREASE SYNERGY (3.12)<br />
Wednesday: 8:30am-12:30pm Room: 1<br />
This session will start with short presentations and<br />
conclude with a panel session.<br />
The session will end with a panel discussions<br />
moderated by Ivo Tripputi (Sogin).<br />
Panelists include: Juan Luis Santiago (Enresa), Jim<br />
Marra (US DOE), and Gerard Laurent<br />
(EDF/CIDEN)<br />
SESSION 38: YOUNG GENERATION NETWORK<br />
(YGN) AND PROFESSIONAL DEVELOPMENT<br />
PROGRAMS (5.17)<br />
Wednesday: 10:45am - 12:30pm Room: 5<br />
A general YGN Meeting will be conducted to canvass<br />
views of the younger members of the industry,<br />
exchange knowledge across companies, and grow the<br />
YGN network through the conference attendees. This<br />
meeting will be used to share best practices, and<br />
develop new ideas to progress the aims and objectives<br />
of the YGN in the future. Agenda: 1) Introductions; 2)<br />
Explanation of YGN Aims and Objectives; 3)<br />
Discussion on Output of YGN Questionnaire; 4)Sharing<br />
of International YGN Activities and <strong>Events</strong>; 5) Personal<br />
Development and Career Progression; 6) Education and<br />
Training Initiatives; 7) Communications across the<br />
YGN Network; 8) External Communications to wider<br />
industry and 9) Future Plans and New Initiatives.<br />
For the session we conduct ‘An audience with…….’<br />
where two leaders of industry provide candid views of<br />
their career paths and offer advice to young<br />
professionals answering any questions and providing<br />
advice on career development.<br />
Panelists Include: Sarah Greenwood, AREVA (UK);<br />
and Jim Blankenhorn, Permafix Environmental<br />
Services Inc.; and Claudio Pescatore, OECD/NEA<br />
(France)<br />
SESSION 48: RADIUM REMEDIATION -<br />
HISTORICAL PERSPECTIVES AND CURRENT<br />
CIRCUMSTANCES - PART 3 OF 3 (4.13)<br />
Wednesday: 4:15pm - 6:00pm Room: 1<br />
An international panel will discuss and compare<br />
progress and history of national radium remediation<br />
programs. Lessons learned will be featured and shared.<br />
The outlook for the final closure on this issue<br />
worldwide will also be addressed. The perspectives and<br />
panelists invited include those from practitioners in<br />
government policy leadership, regulatory oversight and<br />
licensing, health and safety impacts and protection,<br />
environmental remediation practice and affected<br />
community stakeholders.<br />
Panelists Include: Stéphane Pepin, FANC (Belgium);<br />
Keith McConnell, USNRC (USA); Jean-Luc<br />
Lachaume, ASN (France); and Steve Brown, SENES<br />
Consultants Ltd. (USA)
SESSION 49 AND 50: COMMUNICATIONS AND<br />
KNOWLEDGE MANAGEMENT - PART 1 OF 2<br />
(5-21)<br />
Wednesday: 1:45pm - 3:30pm Room: 4<br />
Wednesday: 4:15pm - 6:00pm Room: 4<br />
This is a two part series of paper presentations and a<br />
following panel session discussion on communications<br />
and knowledge management. Current efforts and views<br />
will be presented during this first session. This session<br />
is directly followed by the second part, Panel Session<br />
#50. Presenters will each provide a 10-15 minute<br />
overview to the audience before the break, and will then<br />
resume on this topic.<br />
Panelists Include: Laurie Judd, NuVision<br />
Engineering (USA); Leonel Lagos, Florida<br />
International University (USA); Yanko Yanev, IAEA<br />
(Austria); Hitoshi Makino, JAEA (Japan); Bill<br />
Shingler, Fluor Government Group (USA) and Herve<br />
Bienvenu, Andra (France)<br />
Conference Scheduling and<br />
Additional Information<br />
Registration Hours<br />
DAY / DATE TIME<br />
Sunday, September 25, 2011 4:00pm to 7:00pm<br />
Monday, September 26, 2011 7:15am to 6:00pm<br />
Tuesday, September 27, 2011 7:15am to 6:00pm<br />
Wednesday, September 28, 2011 7:15am to 6:00pm<br />
Thursday, September 29, 2011 7:15am to 12:30pm<br />
Exhibition Hours<br />
DAY / DATE TIME<br />
Monday, September 26, 2011 12:00pm to 6:00pm<br />
Tuesday, September 27, 2011 8:30am to 8:00pm<br />
Wednesday, September 28, 2011 8:30am to 5:00pm<br />
Thursday, September 29, 2011 8:30am to 11:00am<br />
Coffee/Tea Breaks<br />
Complimentary coffee and tea will be served for all<br />
meeting participants at 8:00 am, during the morning<br />
breaks and the afternoon breaks each day of the<br />
conference.<br />
Coffee/Tea Break Schedule<br />
DAY / DATE / TIME LOCATION<br />
Monday, September 26, 2011 RCC - 2nd Floor<br />
8:00am - 9:00am “Le Bouchon” Space<br />
Monday, September 26, 2011 RCC - 2nd Floor<br />
After Third Speaker “Le Bouchon” Space<br />
Monday, September 26, 2011 RCC - Exhibition Hall<br />
3:30pm - 4:10pm 1st Floor<br />
Tuesday, September 27, 2011 RCC - Exhibition Hall<br />
10:15am - 10:40am &<br />
3:30pm - 4:10pm<br />
1st Floor<br />
Wednesday, September 28, 2011 RCC - Exhibition Hall<br />
10:15am - 10:40am &<br />
3:30pm - 4:10pm<br />
1st Floor<br />
Thursday, September 29, 2011 RCC - Exhibition Hall<br />
10:15am - 10:40am 1st Floor<br />
Lunch Periods<br />
Lunch will be served in the Exhibit Hall on Monday,<br />
Tuesday and Wednesday. Lunch serving hours are from<br />
12:30-1:15 pm. Paid full week registration includes the<br />
luncheon price for all three days. If you prefer, there are<br />
also several local restaurants near the conference center.<br />
A listing of local restaurants can be found at<br />
http://www.reims-tourisme.com/a copy of which will be<br />
given to delegates upon arrival.<br />
Lunch Periods<br />
DAY / DATE / TIME LOCATION<br />
Monday thru Wednesday RCC - Exhibition Hall<br />
12:30pm - 1:30pm 1st Floor<br />
Thursday<br />
On your own<br />
N/A<br />
Daily Speaker/Session Co-Chair Briefing<br />
Monday thru Thursday Mornings: 7:30am - 8:00am<br />
RCC, Room: “Le Millesime” Space, 1st Floor<br />
A morning briefing will be provided to all Speakers,<br />
Panelists, Poster Presenters, and Session Co-Chairs on<br />
the day of their session. The briefing will include<br />
coffee/tea and will be served at the conference center.<br />
Most hotels have breakfast included in the cost of the<br />
room, but the speaker’s briefing will give you the time<br />
for final arrangements before your session. The<br />
attendance at the briefing will provide an opportunity<br />
for the Session Co-Chairs to meet with the speakers,<br />
and for all to discuss the topics they will be addressing.<br />
9
10<br />
Presentation Times<br />
The below approximate presentation times are provided<br />
so you can tentatively arrange your schedule. We rely<br />
on the Session Co-Chairs to manage the presentations<br />
to this schedule so that you can move between sessions<br />
and attend the presentations you desire. We recognize<br />
however that due to cancellations or other unplanned<br />
events, the order time may be changed at the<br />
conference. The session posters outside each speaking<br />
room are intended to show the cancelled papers and any<br />
changed times. We also encourage the Session Co-<br />
Chairs to manage the session time in the best interest<br />
for the majority of the attendees and request that they<br />
mark any changes on the posters before the session<br />
starts. We offer our regrets if you missed a presentation<br />
due to these changes.<br />
Approximate Presentation Times<br />
AM START TIME PM START TIME<br />
Session Start 8:30 Session Start 1:45<br />
Paper 1 8:35 Paper 1 1:50<br />
Paper 2 9:00 Paper 2 2:15<br />
Paper 3 9:25 Paper 3 2:40<br />
Paper 4 9:50 Paper 4 3:05<br />
Break 10:15-10:40 Break 3:30-4:10<br />
Session Start 10:45 Session Start 4:15<br />
Paper 5 10:50 Paper 5 4:20<br />
Paper 6 11:15 Paper 6 4:15<br />
Paper 7 11:40 Paper 7 5:10<br />
Paper 8 12:05 Paper 8 5:35<br />
Session Ends 12:30 Session Ends 6:00<br />
Lunch Break 12:30-1:40<br />
Conference Proceedings on CD-ROM<br />
Each conference registrant will receive the conference<br />
proceedings on a CD-ROM mailed approximately six<br />
months after the conference. Additional proceedings<br />
may be ordered at an additional charge, by writing to<br />
the ASME Order Department, 22 Law Drive, P.O. Box<br />
2300, Fairfield, NJ 07007-2300, U.S.A., Telephone 1-<br />
800-THE-ASME.<br />
AV Office / Speaker Ready Area<br />
The AV Office / Speaker Ready area will be available<br />
for speakers to load and review their PowerPoint slides.<br />
This area will be open Sunday from 4:00pm - 7:00pm,<br />
Monday thru Wednesday from 7:15am - 5:00pm, and<br />
Thursday from 7:15am - 12:30pm at the RCC Centre in<br />
the Salle De Presse on the 2nd Floor. The on-site<br />
loading schedule of PowerPoint presentations are listed<br />
below.<br />
Coffee/Tea DAY / DATE Break / TIMESchedule LOCATION<br />
Sunday — 3:00pm-7:00pm<br />
Loading All Power Points All Sessions 1-60<br />
Monday — 9:00am-12:30pm<br />
Reserved for Loading<br />
Monday Afternoon Sessions Sessions 2-9<br />
Monday — 2:00pm-5:00pm<br />
Loading All Power Points Sessions 10-60<br />
Tuesday — 9:00am-12:30pm<br />
Reserved for Loading<br />
Tuesday Afternoon Sessions Sessions 20-28<br />
Tuesday — 2:00pm-5:00pm<br />
Loading All Power Points Sessions 29-60<br />
Wednesday — 9:00am-12:30pm<br />
Reserved for Loading<br />
Wednesday Afternoon Sessions Sessions 40-49<br />
Wednesday — 2:00pm-5:00pm<br />
Loading All Remaining Power Points Sessions 50-60<br />
Poster Session Setup Date and Time<br />
Poster Presentations will be located in the Exhibit Hall<br />
on Level 1 of the Conference Center. Each day of the<br />
conference a Q&A time is set up to meet with the<br />
Poster Presenters. At the end of each session there will<br />
be three Poster Presentations selected as “Best of<br />
Show”. These winning selections will remain until the<br />
end of the conference. We ask that you check back each<br />
day for these selections and on Thursday to view all of<br />
the awardees.<br />
Day Monday Tuesday Wednesday Thursday<br />
Session # 9 19 39 A/B/C 60<br />
Poster 8:00 - 8:00 - 8:00 - Best of<br />
Setup 12:00 8:30 8:30 Show<br />
Poster 12:00 - 8:30 - 8:30 - 8:30 -<br />
Period 5:45 5:45 5:45 11:00<br />
Q&A 12:30 - 10:15 - 10:15 - x<br />
Period 1:30 10:40 10:40<br />
Q&A 3:30 - 3:30 - 3:30 - x<br />
Period 4:10 4:10 4:10<br />
Poster 5:45 - 5:45 - 5:45 - 11:00 -<br />
Removal 6:00 6:00 6:00 12:30
Acronym List<br />
AEA Atomic Energy Agency<br />
ALARA As Low As Reasonably Achievable<br />
ANDRA Agence nationale pour la gestion des<br />
déchets radioactifs<br />
ASME American Society of Mechanical Engineers<br />
BWR Boiling Water Reactor<br />
CEA Commissariat à l’Energie Atomique et aux<br />
Energies Alternatives<br />
CERCLA Comprehensive Environmental Response,<br />
Compensation and Liability Act<br />
CH-TRU Contact Handled Transuranic Waste<br />
DAW Dry Activated Waste<br />
DNFSB Defense Nuclear Facilities Safety Board<br />
DOE Department of Energy<br />
EIS Environmental Impact Statement<br />
EM Environmental Management<br />
EPA Environmental Protection Agency<br />
EPRI Electric Power Research Institute<br />
ER Environmental Remediation<br />
FUSRAP Formerly Utilized Sites Remedial Action<br />
<strong>Program</strong><br />
HEPA High Efficiency Particulate Air<br />
HEU Highly Enriched Uranium<br />
HLW High Level Waste<br />
IAEA International Atomic Energy Agency<br />
IDN International Decommissioning Network<br />
ILW Intermediate Level Waste<br />
IPSN Institut de Protection et de SureteNucleaire<br />
ISM Integrated Safety Management<br />
JAERI Japan Atomic Energy Research Institute<br />
KAERI Korea Atomic Energy Research Institute<br />
LEU Low Enriched Uranium<br />
LILW Low-Intermediate Level Waste<br />
LLW Low Level Waste<br />
LSA Low Specific Activity<br />
M&I Management & Integration<br />
M&O Management & Operation<br />
MOX Mixed Uranium-Plutonium Oxide<br />
MW Mixed Waste<br />
Notes<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
N-DA Non-Detectable Activity<br />
NDA Nuclear Decommissioning Authority<br />
NEA Nuclear Energy Agency<br />
NED Nuclear Engineering Division<br />
NEI Nuclear Energy Institute<br />
NEPA National Environmental Policy Act<br />
NI Nuclear Institute<br />
NNSA National Nuclear Security Administration<br />
NORM Natural Occurring Radioactive Material<br />
NPO Nuclear Power Operations<br />
NPP Nuclear Power Plant<br />
NWPA Nuclear Waste Policy Act<br />
OECD Organization for Economic Cooperation &<br />
Development<br />
PRA Probabilistic Risk Analysis<br />
PWR Pressurized Water Reactor<br />
R&D Research & Development<br />
RCC Reims Champagne Congrès Centre<br />
RCRA Resource Conservation and Recovery Act<br />
RH-TR Remote Handled Transuranic Waste<br />
ROC Republic of China<br />
RPV Reactor Pressure Vessel<br />
RW Rad Waste<br />
SFEN Société Française d’Energie Nucléaire<br />
SNF Spent Nuclear Fuel<br />
SRW Solid Radioactive Waste<br />
TENORM Technologically Enhanced Naturally<br />
Occurring Radioactive Material<br />
TRU Transuranic<br />
TRUPACT Transuranic Package Transporter<br />
USACE United States Army Corps of Engineers<br />
USDOD US Department of Defense<br />
USDOE US Department of Energy<br />
USNRC US Nuclear Regulatory Commission<br />
WAC Waste Acceptance Criteria<br />
WIPP Waste Isolation Pilot Plant<br />
WM Waste Management Symposium<br />
WNA World Nuclear Association<br />
Notes<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
________________________________________________<br />
11
12<br />
Reims City Site Map<br />
RCC<br />
Wednesday Banquet<br />
Champagne de Castelnau Caveau<br />
5 rue Gosset<br />
Reims Train Station to Reims<br />
Champagne Congrès (RCC) Centre (15 minute walk)
Reims Road Map and Hotel Locations<br />
Wednesday Banquet<br />
Champagne de Castelnau Caveau<br />
5 rue Gosset<br />
# HOTEL NAME / ADDRESS<br />
3 Grand Hotel des Templiers / 22 rue des Templiers, 51100 Reims<br />
4 Kyriad Reims Center / 7‐9 rue du Général Sarrail, 51100 Reims<br />
5 Grand Hotel Continental / 93 Place Drouet Erlon, 51100 Reims<br />
6 Holiday Inn Garden Court / 46 Rue Buitrette, 51100 Reims<br />
7 Mercure Cathedrale Hotel / 31 Boulevard Paul Doumer, 51100 Reims<br />
11 Best Western – Hotel de la Paix / 9 rue Buirette, 51100 Reims<br />
12 Hotel Porte Mars / 2 place de la République, 51100 Reims<br />
13 Quality Hotel / 37 Boulevard Paul Doumer, 51100 Reims<br />
14 Grand Hotel de l’Univers / 41 Boulevard Foch, 51100 Reims<br />
16 Bristol Hotel / 76 place Drouet d’Erlon, 51100 Reims<br />
20 Hotel Crystal / 86, place Drouet d’Erlon, 51100 Reims<br />
21 Hotel du Grand Nord / 75 Place Drouet, 51100 Reims<br />
22 Express by Holiday Inn / Boulevard Paul Doumer 21, 51100 Reims<br />
23 Ibis Centre Reims / 28 boulevard Joffre, 51100 Reims<br />
28 Suite Hotel / 1 rue Edouart Mignot, 51100 Reims<br />
29 Résidence Clairmarais / 25 Rue Edouard Mignot, 51100 Reims<br />
13
14<br />
Convention Center — Level 0 (Entrance Access)
Convention Center — Level 1 & Level 2<br />
Level 1 — Registration, Exhibits, Poster, and Speaker’s Briefings<br />
A<br />
B<br />
Lounge Area<br />
C<br />
A – Registration/Speaker & Co-Chair Check-In,<br />
B – Poster Area, C – Speaker's Briefing<br />
Level 2 — Opening Sessions and All Technical Sessions<br />
1<br />
2<br />
3<br />
4<br />
5<br />
6<br />
10<br />
D<br />
E<br />
D – Opening Session<br />
1-10 – Technical Session Rooms<br />
E – Sunday Welcome Reception/ Monday Morning Break Area<br />
15
SESSION #<br />
16<br />
Technical <strong>Program</strong> at a Glance<br />
SESSION TITLES<br />
MONDAY AM - SEPTEMBER 26, 2011<br />
1 Opening Session • • • • • Salle Royale 9:00<br />
MONDAY PM - SEPTEMBER 26, 2011<br />
2 PANEL: Approaches for International Collaboration • Room 1 1:45<br />
3 PANEL: Lessons Learned: Chernobyl 25 Years Later, TMI & Other Experiences • Salle Royale 1:45<br />
4 National and International <strong>Program</strong>s for L/ILW Management • Room 2 1:45<br />
5 L/ILW Treatment Technology Development and Implementation • Room 3 1:45<br />
6 Issues and Solutions Related to Spent Fuel, TRU, and HLW Transportation and Disposal • Room 4 1:45<br />
7 National and International ER <strong>Program</strong>s • Room 5 1:45<br />
8 Experiences in ER Clean-Up Methods and Actions • Room 10 1:45<br />
9 POSTER SESSION: Low/Intermediate Level Waste Management Posters • Exhibit Hall 12:00<br />
TUESDAY AM - SEPTEMBER 27, 2011<br />
10 PANEL: Emerging Issues in the Management of I/ILW • Room 1 8:30<br />
11 PANEL: IAEA: How can Networks Improve the Implementation of ER Projects? • Room 4 8:30<br />
12 Waste Minimization, Avoidance, and Recycling • Room 2 8:30<br />
13 HLW, Fissile, TRU and Spent Fuel Short and Long-Term Storage Issues • Room 3 8:30<br />
14 D&D of Power Reactors and Research Reactors • Room 5 8:30<br />
15 The French D&D Activities - Organization, Strategy, Objectives and Experience • Room 10 8:30<br />
16 National and International D&D <strong>Program</strong>s • Room 10 10:45<br />
17 Applying Strategic Planning, Decision-Making and Risk Reduction Methodologies in EM • Room 6 8:30<br />
18 Economic Analyses, Monitoring Strategies and Project Management in EM • Room 6 10:45<br />
19 POSTER SESSION: Spent Fuel, Fissile, Transuranic and HLW Management Posters • Exhibit Hall 8:30<br />
TUESDAY PM - SEPTEMBER 27, 2011<br />
20 Challenges When Selecting Disposal Options in the Light of the New IAEA Classification Scheme • Room 1 1:45<br />
21 PANEL: Interim Storage, Geological Disposal, Partitioning & Transmutation • Room 4 1:45<br />
22 PANEL: Interim Storage, Geological Disposal, Partitioning & Transmutation Issues • Room 4 4:15<br />
23 Advanced L/ILW Conditioning Technologies - Part 1 of 2 • Room 2 1:45<br />
24 L/ILW Waste Characterization, Assay, and Tracking Systems - Part 1 of 2 • Room 2 4:15<br />
25 D&D of Non-Reactor Nuclear Facilities • Room 3 1:45<br />
26 D&D Technologies - Part 1 of 2 • Room 5 1:45<br />
27 ER Site Characterization and Monitoring - Part 1 of 2 • Room 10 1:45<br />
28 Public Perception Issues and Stakeholder Engagement Strategies in Radioactive EM • Room 6 1:45<br />
WEDNESDAY AM - SEPTEMBER 28, 2011<br />
29 PANEL: International Cooperation: NEA Road Map, How to Increase Synergy • Room 1 8:30<br />
30 Siting, Design, Construction, and Operation of L/ILW Disposal Facilities - Part 1 of 2 • Room 2 8:30<br />
31 L/ILW Waste Characterization, Assay, and Tracking Systems - Part 2 of 2 • Room 3 8:30<br />
LLW<br />
HLW<br />
D&D<br />
ER<br />
EM<br />
ROOM #<br />
TIME
SESSION #<br />
Technical <strong>Program</strong> at a Glance<br />
WEDNESDAY AM - SEPTEMBER 28, 2011<br />
32 Repository <strong>Program</strong>s: - Part 1 of 2 • Room 4 8:30<br />
33 Recent Advances in Processing and Immobilization of HLW, Fissile Material and<br />
Transuanic (TRU) - Part 1 of 2 • Room 6 8:30<br />
34 Uranium Sites, ER Issues, Site Characterization and Monitoring - Part 2 of 2 • Room 10 8:30<br />
35 Merged with Session 34<br />
SESSION TITLES<br />
36 Radium Remediatio:- Historical Perspectives and Current Circumstances - Part 1 of 3 • Room 10 10:45<br />
37 Young Generation Network (YGN) and Professional Development <strong>Program</strong>s - Presentations • Room 5 8:30<br />
38 Young Generation Network (YGN) and Professional Development <strong>Program</strong>s - Meeting • Room 5 10:45<br />
39A POSTER SESSION: D&D • Exhibit Hall 8:30<br />
39B POSTER SESSION: ER • Exhibit Hall 8:30<br />
39C POSTER SESSION: EM & Crosscutting • Exhibit Hall 8:30<br />
WEDNESDAY PM - SEPTEMBER 28, 2011<br />
40 D&D Management Approaches and Planning Tools • Room 2 1:45<br />
41 D&D Technologies - Part 2 of 2 • Room 3 1:45<br />
42 Liquid Waste Treatment Process and Experience • Room 5 1:45<br />
43 Siting, Design, Construction, and Operation of L/ILW Disposal Facilities - Part 2 of 2 • Room 6 1:45<br />
44 Disposal Site and Waste Form Characterization and Performance Assessment - Part 1 of 2 • Room 6 4:15<br />
45 Repository <strong>Program</strong>s: - Part 2 of 2 • Room 10 1:45<br />
46 National and International <strong>Program</strong>s for Spent Fuel, Fissile, TRU, and HLW Management • Room 10 4:15<br />
47 Radium Remediation - Historical Perspectives and Current Circumstances - Part 2 of 3 • Room 1 1:45<br />
48 PANEL: Radium Remediation Historical Perspectives and Current Circumstances - Part 3 of 3 • Room 1 4:15<br />
49 PANEL: Communications and Knowledge Management - Part 1 of 2 • Room 4 1:45<br />
50 PANEL: Communications and Knowledge Management - Part 2 of 2 • Room 4 4:15<br />
THURSDAY AM - SEPTEMBER 29, 2011<br />
51 Safety Considerations Associated with L/ILW Management • Room 2 8:30<br />
52 Disposal Site and Waste Form Characterization and Performance Assessment - Part 2 of 2 • Room 3 8:30<br />
53 Global Partnership in Environmental Management - Part 1 of 2 • Room 1 8:30<br />
54 Global Partnership in Environmental Management - Part 2 of 2 • Room 1 10:45<br />
55 Safety and Security Related to Environmental and Nuclear Materials Management • Room 4 8:30<br />
56 Advanced L/ILW Technologies - Part 2 of 2 • Room 4 10:45<br />
57 Recent Advances in Processing and Immobilization of HLW, Fissile and TRU - Part 2 of 2 • Room 5 8:30<br />
58 D&D Radiological Characterization and Monitoring • Room 10 8:30<br />
59 Risk/Performance Assessments and Contaminant Migration • Room 6 8:30<br />
60 POSTER SESSION: Best Posters of ICEM2011 • • • • • Exhibit Hall 8:30<br />
LLW<br />
HLW<br />
D&D<br />
ER<br />
EM<br />
ROOM #<br />
TIME<br />
17
Monday AM Technical Sessions<br />
Presentations with a paper prepared for the post conference CD are<br />
noted as “wP”. Presentations without papers are noted as “w/oP”.<br />
Authors and Panelists speaking are shown in Bold. Coffee will be<br />
served at 8:00am, Tuesday - Thursday in Lounge A in the Exhibit Hall.<br />
SESSION 1<br />
Monday: 9:00am -12:30pm Room: Salle Royale<br />
PLENARY SESSION<br />
Co-Chairs: Yvette Collazo, US DOE (USA)<br />
Dominique Grenêche, SFEN (France)<br />
The Opening Session will begin Monday morning with the keynote<br />
presentations setting the theme for this year’s conference. Coffee will<br />
be served on the 2nd floor Foyer from 08:00 until the program begins<br />
at 9:00am.<br />
• Welcome to the ICEM’11 Conference —<br />
Yvette Collazo, for ASME (USA)<br />
• Welcome to Reims —<br />
Dominique Grenêche for SFEN (France)<br />
Plenary Speakers:<br />
• Mr. Christophe Behar, Nuclear Energy Director, CEA (France)<br />
• Ms. Tracy Mustin, Principal Deputy Assistant Secretary for EM,<br />
DOE (USA)<br />
• Mr. Francois-Michel Gonnot, Chairman of the Board, Andra<br />
(France)<br />
— BREAK —<br />
• Dr. Tero Varjoranta, Director, Division of Nuclear Fuel Cycle and<br />
Waste Technology, IAEA (Austria)<br />
• Mr. Arnaud Gay, Executive Vice President of the Nuclear Sites<br />
Value Development Business Unit, AREVA (France)<br />
• Conference Organization and Administration: Gary Benda,<br />
ICEM Conference Manager (USA)<br />
SESSION 2<br />
Monday: 1:45pm - 6:00pm Room: 1<br />
PANEL: APPROACHES FOR INTERNATIONAL<br />
COLLABORATION (5.18)<br />
Co-Chairs: Rosa Ramirez, US DOE (USA)<br />
John Mathieson, UK Nuclear Decommissioning<br />
Authority (UK)<br />
Organizers: Ana Han, US DOE<br />
An important element to reducing the cost and schedule of a country’s<br />
and/or organization’s environmental remediation mission is<br />
forming key international collaborative partnerships that focus on<br />
identifying and leveraging international expertise, infrastructure, and<br />
collaboration opportunities. This panel will provide an overview of<br />
the different approaches and initiatives used to promote international<br />
collaboration in environmental remediation and/or radioactive waste<br />
management, with a focus on the challenges and opportunities unique<br />
to each country and/or organization.<br />
Panelists include: Mark Butez, Andra (France); John Mathieson,<br />
NDA (UK); Ian Bainbridge, AECL (Canada); Jong-Kil Park,<br />
KHNP (Korea); Malgorzata K. Sneve, Norwegian Radiation Protection<br />
Authority (Norway)<br />
SESSION 3<br />
Monday: 1:45pm - 6:00pm Room: Salle Royale<br />
PANEL: LESSONS LEARNED: FUKUSHIMA, CHERNOBYL-<br />
25 YEARS LATER, TMI-2 & OTHER EXPERIENCES (3.11)<br />
Co-Chairs: Jas S. Devgun, Sargent & Lundy (USA)<br />
Jean-Guy Nokhamzon, CEA/DEN/DADN<br />
(France)<br />
Organizers: Jas S. Devgun and Jean-Guy Nokhamzon<br />
This panel was initially planned to discuss confinement activities and<br />
lessons learned from Chernobyl at a time of 25th anniversary of the<br />
Chernobyl accident (April 26, 1986), lessons from TMI-2 accident<br />
(March 28, 1979) and other industry experience with smaller events.<br />
However, the natural events of March 11, 2011 (large earthquake and<br />
18<br />
tsunami) led to the accident at the Fukushima- Dai-ichi complex<br />
which has been given the highest rating of seven on the international<br />
scale, equivalent to that of the 1986 Chernobyl crisis. The recovery<br />
efforts at Fukushima are still ongoing. This panel will discuss lessons<br />
learned from Fukushima, Chernobyl, and TMI-2 related to recovery,<br />
confinement, decommissioning, and future design lessons.<br />
Panelists include: Dr. Tero Varjoranta, IAEA (Austria); Sergii<br />
Mitichkin, Chernobyl NPP (Ukraine); Thomas Chauveau,<br />
Bouygues-Construction (France); Didier Dall’ava,<br />
CEA/DEN/DADN (France); Svetlana Bratskaya, Institute of Chemistry<br />
of Russian Academy of Science (Russia); and Dominique<br />
Greneche, SFEN (France)<br />
SESSION 4<br />
Monday: 1:45pm - 6:00pm Room: 2<br />
NATIONAL AND INTERNATIONAL PROGRAMS FOR L/ILW<br />
MANAGEMENT (1.2)<br />
Co-Chairs: Andrew Baker, Eden Nuclear and Environment<br />
Ltd. (UK)<br />
Michel Dutzer, Andra (France)<br />
Organizers/Reviewers: Keith Anderson and David Wallace<br />
1. Low Level Waste Disposal Regulatory Issues in the US<br />
(w/oP-59311)<br />
David James, Thomas Kalinowski, DW James Consulting LLC;<br />
Lisa Edwards, Electric Power Research Inst. (USA)<br />
2. Taking the UK’s National LLW Progamme from Strategy<br />
Development to Implementation (w/oP-59059)<br />
David Rossiter, Rachel O’Donnell, LLW Repository Ltd. (UK)<br />
3. CEA’s Waste Management Policy and Strategy. Lessons<br />
Learned (w/oP-ICEM2011-59201)<br />
Didier Dall’ava, CEA (France)<br />
4. Regulations for the Disposal of Radioactive Waste in the<br />
Konrad Repository (w/oP-ICEM2011-59105)<br />
Hagen Gunther Jung, Lower Saxony Water Management,<br />
Coastal Protection and Nature Conservation Agency (NLWKN);<br />
Gabriele Bandt, TÜV Nord EnSys Hannover GmbH & Co. KG<br />
(Germany)<br />
— BREAK —<br />
5. The Hydrogeologic Environment for a Proposed Deep<br />
Geologic Repository in Canada for Low and Intermediate<br />
Level Radioactive Waste (w/oP-59285)<br />
Jonathan Sykes, Stefano Normani, Yong Yin, University of<br />
Waterloo; Mark Jensen, Nuclear Waste Management<br />
Organization (Canada)<br />
6. Radioactive Waste Management Challenges and Progress in<br />
Iraq (wP-59164)<br />
Fouad Al-Musawi, Emad Shamsaldin, Ministry of Science &<br />
Technology (Iraq); John Cochran, Sandia National Laboratories<br />
(USA)<br />
SESSON 5<br />
Monday: 1:45pm - 6:00pm Room: 3<br />
L/ILW TREATMENT TECHNOLOGY DEVELOPMENT AND<br />
IMPLEMENTATION (1.15)<br />
Co-Chairs: Hans Codee, COVRA N.V. (Netherlands)<br />
Keith Anderson, ECC (USA)<br />
Organizers/Reviewers: Hans Codee and Keith Anderson<br />
1. Research and Technology Delivery at Sellafield, UK (w/oP-<br />
59372)<br />
Mike James, Sellafield Ltd (UK)<br />
2. Waste Loading Enhancements for Hanford LAW Glasses<br />
(wP-59018)<br />
Albert Kruger, US Department of Energy WTP Engineering<br />
Division (USA)<br />
3. THOR(R) Steam Reforming Technology for the Treatment<br />
of Complex and Problematic Wastes (wP-59084)<br />
J. Brad Mason, Adam L. Foster, Studsvik, Inc.(USA)
Technical Sessions Monday PM<br />
4. A Room Temperature Stabilization and Waste Volume<br />
Reduction Method Tested on Belgian Intermediate-Level<br />
Homogeneous Bituminized Waste (Eurobitum) (wP-59103)<br />
Nathalie R.E.N. Impens, SCK-CEN; Jan Deckers,<br />
BelgoProcess; Lesley Adriaensen, Pierre Van Iseghem,<br />
Studiecentrum voor Kernenergie-Centre d’Etude de l’Energie<br />
Nucléaire (Belgium) — BREAK —<br />
5. Standardizing of LLW/ILW Treatment for Russian Type<br />
Pressure Water Reactors (w/oP-59233)<br />
Klaus Buettner, Rainer Slametschka, NUKEM Technologies<br />
GmbH (Germany)<br />
6. 35 Years of Incineration in Studsvik, Lessons Learned and<br />
Recent Modifications and Improvements (wP-59264)<br />
Maria Lindberg, Karin von Kronhelm, Joakim Lövstrand,<br />
Studsvik Nuclear AB (Sweden)<br />
7. Sodium-Rich Wastes: Challenges, Analysis and Performance<br />
(w/oP-59316)<br />
Daniel Brew, Melody L Carter, Lou Vance, Martin W Stewart,<br />
ANSTO (Australia)<br />
8. Preliminary Demonstration of GeoMelt Treatment of<br />
Hanford’s K-Basin Sludge (wP-59004)<br />
Keith Witwer, IMPACT Services, Inc. (USA)<br />
SESSION 6<br />
Monday: 1:45pm - 6:00pm Room: 4<br />
ISSUES AND SOLUTIONS RELATED TO SPENT FUEL, TRU,<br />
AND HLW TRANSPORTATION AND DISPOSAL (2-5)<br />
Co-Chairs: Mike Garamszeghy, Nuclear Waste Management<br />
Organization (Canada)<br />
Jean Paul Chiles, Ecole Mines (France)<br />
Organizers/Reviewers: Jeffrey Griffin and Jean Paul Chiles<br />
1. Initial Assessment of Radon in a Deep Geological Repository<br />
for Used Nuclear Fuel (wP-59145)<br />
Kelly Sedor, Frank Garisto, Helen Leung, Nuclear Waste<br />
Management Organization (Canada)<br />
2. Groundwater Flow Modeling of Periods with Temperate<br />
Climate Conditions for use in a Safety Assessment of a<br />
Repository for Spent Nuclear Fuel (w/oP-59154)<br />
Steven Joyce, Lee Hartley, Serco; Trevor Simpson, Serco (UK)<br />
3. Conception of a New Conditioning Process, of Strongly<br />
Plutonium Contaminated Waste Canisters (w/oP-59205)<br />
Maxime Michel-Noel, ONET Technologies-ONECTRA (France)<br />
4. Methodological Guide on Development of Work Plan for<br />
Mitigation of Accident Consequences during Transportation<br />
of Radioisotope Thermoelectric Generators and<br />
Radioisotope Heat Sources (w/oP-59162)<br />
Valeriy Shempelev, Scientific and Engineering Centre for<br />
Nuclear and Radiation Safety; Vladimir Reka, Rostechnadzor;<br />
Malgorzata Sneve, Norwegian Radiation Protection Authority;<br />
Alexander Smetnik, Evgenij Kapralov, FSUE VO “Safety”;<br />
Galina Zubareva, Tver State Medical Academy (Russia/Norway)<br />
— BREAK —<br />
5. Physical and Chemical Processes during Vacuum Drying of<br />
Metallic Spent Nuclear Fuel (wP-59114)<br />
Martin Plys, Michael Epstein, Sung Jin Lee, Robert Apthorpe,<br />
Fauske & Associates LLC (USA)<br />
6. Security Issues for Long-Term Storage of Used Fuel<br />
(w/oP-59380)<br />
Felicia A Durán, Gregory Wyss, Calvin Jaeger, Sandia National<br />
Laboratories (USA)<br />
SESSION 7<br />
Monday: 1:45pm-6:00pm Room: 5<br />
NATIONAL AND INTERNATIONAL ER PROGRAMS (4.2)<br />
Co-Chairs: Leo P.M. Velzen, Nuclear Research and<br />
Consultancy Group (Netherlands)<br />
Nick DiMascio, Bartlett Services Inc. (USA)<br />
Organizers/Reviewers: Steve Brown and Leo Van Velzen<br />
1. Objectives for Remediation of Areas Polluted by Radioactive<br />
Substances in France (w/oP-59300)<br />
Charlotte Cazala, Didier Gay, Olivier Chabanis, Jerome<br />
Guillevic, IRSN; Odile Palut Laurent, Geraldine Dandrieux,<br />
ASN; Alain Thomassin, IRSN/DRPH/SER/UETP; Chapalain<br />
Estelle, Laurence Roy, Ministère de lEcologie, du<br />
Développement Durable, des Transports et du Logement<br />
(France)<br />
2. Remediation of AREVA Miramas Site (w/oP-59312)<br />
Gilles Potier, AREVA (France)<br />
3. The Value of a Mature, Stable, and Transparent Regulatory<br />
Framework in Facilitating ER <strong>Program</strong>s Lessons Learned in<br />
Decommissioning of Uranium Recovery and Other Facilities<br />
in the USA (w/oP-59411)<br />
Keith I. McConnell, Larry Camper, U.S. Nuclear Regulatory<br />
Commission (USA)<br />
4. The First New Conventional Uranium Mill in the U.S. in 30<br />
Years Licensing of the Pinon Ridge Project, Colorado, USA<br />
(w/oP-59330)<br />
Steve Brown, SENES Consultants Ltd; Frank Filas, Energy<br />
Fuels Resources, Lakewood, (USA)<br />
— BREAK —<br />
5. Integrated <strong>Program</strong> Management for Major Nuclear<br />
Decommissioning and Environmental Remediation Projects<br />
(w/oP-59068)<br />
John Lehew, CH2M Hill Plateau Remediation Company (USA)<br />
6. EPRI Nuclear Power Plant Groundwater Protection<br />
<strong>Program</strong> (w/oP-59341)<br />
Karen Kim, Electric Power Research Institute (USA) -<br />
Presentation by Sean Bushart, EPRI (USA)<br />
7. Clean Up Strategies and Results in USIN Site in São Paulo<br />
City, Brazil (w/oP-59243)<br />
Rodrigo Raposo de Almeida, Federal Fluminense University;<br />
Valter J.G. Mortágua, Industrias Nucleares do Brasil (Brazil)<br />
8. Application of an Environmental Remediation Methodology:<br />
Theory vs. Practice. Reflections and Two Belgian Case<br />
Studies (wP-59184)<br />
Koen Mannaerts, Stephane Pepin, Boris Dehandschutter, Walter<br />
Blommaert, Federal Agency for Nuclear Control (FANC)<br />
(Belgium)<br />
SESSION 8<br />
Monday: 1:45pm - 6:00pm Room: 10<br />
EXPERIENCES IN ER CLEAN-UP METHODS AND ACTIONS<br />
(4.4)<br />
Co-Chairs: Dawn Kaback, AMEC (USA)<br />
Virgene Mulligan, ARS International, Inc. (USA)<br />
Organizers: Didier Dubot and Steve Brown<br />
Reviewers: Susan Walter and Walter Van Hecke<br />
1. Groundwater Remediation of Hexavalent Chromium along<br />
the Columbia River at the Hanford Site in Washington State,<br />
USA (wP-59030)<br />
Dyan Foss, CH2M Hill Plateau Remediation Company; Briant<br />
Charboneau, DOE RL (USA)<br />
2. Environmental Remediation of an Alstom Grid Industrial<br />
Site (France) (wP-59270)<br />
Stéphanie Romero, ALSTOM GRID (France)<br />
3. Design and Installation of a Permeable Treatment Wall to<br />
Passively Remove Strontium-90 from Groundwater at a<br />
Former Commercial Nuclear Fuel Reprocessing Facility in<br />
New York (wP-59292)<br />
Douglas Bablitch, Rupeet Malhotra, Richard Frappa, Scott<br />
Warner, AMEC Geomatrix (USA)<br />
19
Monday PM Technical Sessions<br />
4. Decommissioning of the Active Storage Facility for Residuals<br />
in Rheinsberg (Brandenburg/Germany) and Results of<br />
Groundwater Monitoring (wP-59134)<br />
Mathias Steinhoff, Öko-Institut e.V. (Germany)<br />
— BREAK —<br />
5. Environmental Surveillance System for the Shchuchye Site<br />
(wP-59042)<br />
Stephane Belbeze, Matthieu Hallouin, Antea (France)<br />
6. 25 Years After Chernobyl NPP Accident: Experience and<br />
Trends of Radioactive Contaminated Soils Rehabilitation in<br />
Belarus (wP-59242)<br />
Leanid Maskalchuk, JIPNR-Sosny NAS of Belarus (Belarus)<br />
SESSION 9<br />
Monday: 12:30pm - 6:00pm Room: Exhibit Hall<br />
POSTER SESSION: LOW/INTERMEDIATE LEVEL WASTE<br />
MANAGEMENT (1.1)<br />
Co-Chairs: Steve Rima, AMEC (USA)<br />
Cathy Hickey, CH2M Hill (USA)<br />
Reviewers: Donald Goebel, Vickie Maranville, and David Wallace<br />
1. Numerical Modeling for Colloid-Facilitated Migration of N-<br />
Number Radionuclides Chains in the Fractured Rock (w/oP-<br />
59257)<br />
Chun-Ping Jen, National Chung Cheng University (Taiwan)<br />
2. Laboratory Experiments on the Alteration of Highly-<br />
Compacted Bentonite by Alkaline Solution and the Effects<br />
on Physical Properties (wP-59318)<br />
Satoru Miyoshi, Shinya Morikami, Yukinobu Kimura, Tomoko<br />
Jinno, Shuichi Yamamoto, Obayashi Corporation (Japan)<br />
3. Gas Transport Properties of Pumice Tuff for Performance<br />
Assessment of LLW Disposal Facility (wP-59074)<br />
Shuichi Yamamoto, Kenichiro Suzuki, Obayashi Corporation;<br />
Mamoru Kumagai, Japan Nuclear Fuel Limited; Yasuhiro<br />
Tawara, Koji Mori, Geosphere Environmental Technology<br />
Corporation (Japan)<br />
4. Extraction and Confinement of Caesium Using<br />
Functionalized Porous Materials (w/oP-59106)<br />
Carole Delchet, Guillaume Toquer, Agnès Grandjean, Institut de<br />
Chimie Séparative de Marcoule; Joulia Larionova, Yannick<br />
GUARI (France)<br />
5. Photocatalytic and Photochemistry Degradation of Liquid<br />
Waste Containing EDTA (wP-59144)<br />
Célia Lepeytre, Cyril Lavaud, Guillaume Serve, CEA Marcoule<br />
(France)<br />
6. Historical Waste – Biological Shield & Documentation<br />
during Decommissioning (w/oP-59056)<br />
Thomas Nellemann, Anne Sørensen, Danish Decommissioning<br />
(Denmark)<br />
7. A Numerical Interpretation of Density Homogenization of<br />
Bentonite Material in Wetting Process (wP-59153)<br />
Atsushi Iizuka, Yusuke Takayama, Katsuyuki Kawai, Kobe<br />
University; Shinya Tachibana, Saitama University; Shintaro<br />
Ohno, Ichizo Kobayashi, Kajima Corporation (Japan)<br />
8. Comparison of Organic and Inorganic Ion Exchangers for<br />
the Treatment of Radioactive Liquid Wastes by Ion<br />
Exchange Processes (w/oP-59107)<br />
Yves Barre, CEA (France)<br />
9. Detritiation of JET Plasma Facing Components (w/oP-<br />
59345)<br />
Pierre Trabuc, Karine Liger, Nicolas Ghirelli, Christophe<br />
Perrais, CEA (France)<br />
10. Experimental Drop Testing of Waste Containers for the<br />
KONRAD Repository (w/oP-59269)<br />
Tino Neumeyer, Karsten Müller, Holger Voelzke, Federal<br />
Institute for Materials Research and Testing (BAM) (Germany)<br />
11. Instrumented Measurements on Radioactive Waste Disposal<br />
Containers during Experimental Drop Testing (wP-59142)<br />
Thomas Quercetti, Andre Musolff, Karsten Müller, BAM -<br />
Federal Institute for Materials Research and Testing (Germany)<br />
20<br />
12. Regulatory Clearance of Spent Steel Drums (wP-59405)<br />
Dae-Seok Hong, Korea Atomic Energy Research Institute;<br />
Young-Yong Ji, Il-Sik Kang, Kyoung-Kil Kwak, Woo-Seog Ryu,<br />
KAERI (Korea)<br />
13. Liquid Waste Treatment Process (w/oP-59061)<br />
Bouchta Moussaif, Touria Lambarki el Allioui, CNESTEN<br />
(Morocco)<br />
14. Cast Iron Transport, Storage and Disposal Containers for<br />
use in UK Nuclear Licensed Sites (w/oP-59412)<br />
Joerg Viermann, Matthias P Messer, GNS Gesellschaft fuer<br />
Nuklear-Service mbH (UK)<br />
15. Optimization of Radioactive Waste Cementation for<br />
Decommissioning of Salaspils Research Reactor (wP-59066)<br />
Gunta Abramenkova, Maris Klavins, University of Latvia;<br />
Andris Abramenkovs, Latvian Environment, Geology and<br />
Meteorology Centre (Latvia)<br />
16. Bayesian Statistics Applied to the Activities of Waste Drums<br />
(wP-59081)<br />
Richard Bull, Ian Adsley, Nuvia Limited (UK)<br />
17. Physical Modelling of Turbulent Jets for Nuclear Sludge<br />
Mobilisation (wP-59147)<br />
Donna McKendrick, Institute of Particle Science and<br />
Engineering; Simon Biggs, Michael Fairweather, James Young,<br />
University of Leeds (UK)<br />
18. Environmentally-Friendly Recovery of Uranium from<br />
Nuclear Fuel Scraps Generated at Nuclear Fuel Fabrication<br />
Process (wP-59383)<br />
Kwang-Wook Kim, Dong-Yong Chung, Eil-Hee Lee, Keun-<br />
Young Lee, Kune Woo Lee, Jei-Kwon Moon, Korea Atomic<br />
Energy Research Insititute (Korea)<br />
19. Self Cleaning HEPA Filtration Without Interrupting Process<br />
Flow (wP-59347)<br />
Chris Chadwick, Porvair Filtration Group (UK)<br />
20. Steam and Condensate Tolerant HEPA Filter - Substitute for<br />
ESP (wP-59346)<br />
Chris Chadwick, Porvair Filtration Group (UK)<br />
21. Status of Site Investigation for L/ILW Facilities in the<br />
Philippines (wP-59262)<br />
Maria V. Palattao, Carl Nohay, Rolando Reyes, Alfonso<br />
Singayan, Philippine Nuclear Research Institute (Philippines);<br />
Dirk Mallants, Belgian Nuclear Research Centre SCK-CEN<br />
(Belgium)<br />
22. Management of Smoke Detectors Containing Radioactive<br />
Sources (wP-59049)<br />
Mercedes Salgado Mojena, Juan Carlos Benitez Navarro, Juan<br />
Miguel Hernandez García, Rafael Castillo Gomez, Ania<br />
Berdellans Escobar, CPHR (Cuba); Carlos Jose Pirez, Pedro<br />
Graciano Soto, Atomic Centre Ezeiza, National Commission of<br />
Atomic Energy (Argentina)<br />
23. Curing Time effect on the Fraction of 137 CS from<br />
Immobilized Radioactive Evaporator Sludge by Cement<br />
(wP-59006)<br />
Ilija Plecas, Slavko Dimovic, Vinca Institute of Nuclear<br />
Sciences; Radojica Pesic, Nuclear Facilities of Serbia (Serbia)<br />
24. An Approach for the Development of a Comprehensive Data<br />
Base of Time-Dependent Hydraulic and Transport<br />
Parameters for Concrete Engineered Barriers (wP-59299)<br />
Suresh Seetharam, Dirk Mallants, Janez Perko, Diederik<br />
Jacques, SCK.CEN (Belgium)<br />
25. Radiation Protection Experiences in Retrieval of Radioactive<br />
Waste at Püspökszilágy Repository (wP-59054)<br />
László Juhász, National Research Institute for Radiobiology<br />
and Radiohygiene; Sándor Kapitány, István Barnabás, Public<br />
Limited Company for Radioactive Waste Management; Anna<br />
Mária Motoc, National Research Institute for Radiobiology and<br />
Radiohygiene (Hungary)
Technical Sessions Tuesday AM<br />
SESSION 10<br />
Tuesday: 8:30am - 12:30pm Room: 1<br />
PANEL: EMERGING ISSUES IN THE MANAGEMENT OF<br />
I/ILW (1.16)<br />
Co-Chairs: Michel Dutzer, Andra (France)<br />
Angie Jones, AMEC (USA)<br />
Organizer: Michel Dutzer<br />
This panel will focus on strategies for the management of all low and<br />
intermediate level waste (L/ILW). Based on experience in different<br />
national programs, it will discuss various options and their merits for<br />
managing L/ILW. It will consider the definition of different categories<br />
of L/ILW and their potential routes for disposal including waste of<br />
very low activity, often arising in high volumes as contaminated land,<br />
or from decommissioning. There will be discussion on large, disused<br />
components that are part of the decommissioning L/ILW waste<br />
stream. The engineering of facilities for the disposal of all such wastes<br />
should be proportionate to the long-term environmental impact that<br />
might arise.<br />
Panelists include: Irena Mele, Section Head of Waste Technology,<br />
IAEA (Austria); Keith McConnell, Deputy Director, US NRC (USA);<br />
Bruno Cahen, Director, Andra (France); Geraldine Dandrieux,<br />
Head of Waste, Research Facilities and Fuel Cycle Facilities<br />
Department (France); Kazuyuki Kato, Federation of Electric Power<br />
Companies (Japan); Paul Dixon, Los Alamos National Lab (USA);<br />
and Dick Raaz, Chairman and Director, UK LLWR (UK)<br />
SESSION 11<br />
Tuesday: 8:30am-12:30pm Room: 4<br />
PANEL: HOW CAN NETWORKS IMPROVE THE<br />
IMPLEMENTATION OF ER PROJECTS? THE IAEA<br />
NETWORK ON ENVIRONMENTAL MANAGEMENT AND<br />
REMEDIATION-ENVIRONET (4.15)<br />
Co-Chairs: Leo Van Velzen, EURSSEM, NRG (Netherlands)<br />
Rosa Ramirez, US DOE (USA)<br />
Organizer: Horst Monken Fernandes<br />
Environmental remediation projects tend to be constrained by several<br />
aspects being the lack of financial resources one of the most<br />
prominent factors. However, even when financial resources are<br />
available lack of institutional framework (e.g. lack of regulations),<br />
lack of human resources, and absence of a solid technical basis at the<br />
national level will contribute to slow the pace of implementation.<br />
Networking intends to bring problem holders and solution donors<br />
together and enhance the exchange of experience while fostering the<br />
construction of partnerships. The ENVIRONET was initially<br />
presented to the international community at WM 2010. The ICEM<br />
2011 will be an opportunity to present its achievement, broaden its<br />
affiliation and build an agenda of activities for the next years.<br />
Panelists include: Leo van Velzen, NRD (Netherlands); Peter<br />
Booth, WSP Group (UK); and joining after the break - Irena Mele,<br />
Section Head of Waste Technology, IAEA (Austria)<br />
SESSION 12<br />
Tuesday: 8:30am - 12:30pm Room: 2<br />
WASTE MINIMIZATION, AVOIDANCE, AND RECYCLING<br />
(1.3)<br />
Co-Chairs: Ian Beadle, AMEC (UK)<br />
Kapila Fernando, ANSTO (Australia)<br />
Organizers/Reviewers: Ian Beadle and Kapila Fernando<br />
1. Waste Minimization by Melting - Recycling of Radioactive<br />
Metals (wP-59040)<br />
Thomas Kluth, Ulrich Quade, Siempelkamp Nukleartechnik<br />
GmbH (Germany)<br />
2. Waste Minimization Benefits of Dissolvable Protective<br />
Clothing (wP-59003)<br />
Michael Cournoyer, David Wannigman, Robert Dodge, Los<br />
Alamos National Laboratory (USA)<br />
3. Evaluation of External Exposure during Building and<br />
Operation of Concrete Bridges Constructions that Reuse the<br />
Conditionally Released Steels (wP-59120)<br />
Michal Panik, Vladimir Necas, Slovak University of Technology<br />
(Slovakia)<br />
4. Treatment of Spent Acidic Decontaminants with a High-<br />
Efficiency Cementation Method (wP-59063)<br />
Kou-Ming Lin, Ching-Tu Chang, Ming-Shin Wu, Wen-Chen<br />
Lee, Jen-Chieh Chung, Tsong-Yang Wei, Institute of Nuclear<br />
Energy Research (Taiwan)<br />
— BREAK —<br />
5. Methodology for Identification of Conditionally Released<br />
Materials from Decommissioning using the OMEGA Code<br />
(wP-59175)<br />
Matej Zachar, Vladimír Daniaka, DECOM, a.s.; Vladimir<br />
Necas, Slovak University of Technology (Slovakia)<br />
6. Impact of Nuclide Vector Composition Contained in<br />
Conditionally Released Steel Reused In Motorway Tunnels<br />
Scenario on Calculated Individual Effective Doses (wP-<br />
59128)<br />
Tomas Hrncir, Vladimir Necas, Slovak University of Technology<br />
(Slovakia)<br />
7. Evaluation of Technical, Economic and Financial Feasibility<br />
for Recycling and Reprocessing of Radioactive Waste from a<br />
Remediation Work of Low and Medium Activity for the<br />
Extraction of Heavy Minerals (w/oP-59231)<br />
Rodrigo Raposo de Almeida, Federal Fluminense University;<br />
Valter J.G. Mortágua, Industrias Nucleares do Brasil (Brazil)<br />
8. WNA Statement - Towards Greater Efficiency in the<br />
Management of Low-Level Radioactive Material that<br />
Concurrently Supports Reuse, Recycling and Disposal (w/p -<br />
59414)<br />
Sylvain Saint-Pierre, World Nuclear Association (WNA) (UK)<br />
SESSION 13<br />
Tuesday: 8:30am - 12:30pm Room: 3<br />
HLW, FISSILE, TRU AND SPENT FUEL SHORT AND LONG-<br />
TERM STORAGE ISSUES (2.4)<br />
Co-Chairs: Vince Dilworth, ASME (USA)<br />
Organizer: James Blankenhorn, Permafix Environmental<br />
Services Inc. (USA)<br />
Reviewer: Bill Wilmarth<br />
1. West Valley Demonstration Project High Level, Transuranic,<br />
and Greater than Class C Wastes (wP-59048)<br />
James Blankenhorn, West Valley Environmental Services (USA)<br />
2. Managing Aging Effects on Used Fuel Dry Cask for Very<br />
Long-Term Storage (wP-59067)<br />
Omesh Chopra, Dwight Diercks, David Ma, Vik Shah, Shiu-<br />
Wing Tam, Ralph Fabian, Yung Liu, Mark Nutt, Argonne<br />
National Laboratory (ANL)(USA)<br />
3. Application of Coupled Thermo-Hydro-Mechanical-<br />
Chemical (THMC) Process In Hydrothermal Systems To<br />
Process Near A High-Level Nuclear Waste Repository (wP-<br />
59246)<br />
Geoffrey Peter, Oregon Institute of Technology Portland Center<br />
(USA)<br />
4. Generic Design Assessment of Long-Term Spent Fuel<br />
Storage for New Reactors in the UK (wP-59174)<br />
Christopher Fisher, Nuclear Directorate, Health and Safety<br />
Executive; Dave Watson, Office of Nuclear Regulation; Ian<br />
Streatfield, Colette Grundy, Saffron Price-Walter, Environment<br />
Agency, Dave Glazbrook, Office of Nuclear Regulation (UK)<br />
— BREAK —<br />
6. Industrial Complementarities between Interim Storage and<br />
Reversible Geological Repository (wP-59237)<br />
Jean-Michel Hoorelbeke, Andra (France)<br />
7. Recent Developments in Spent Fuel Management in Norway<br />
(wP-59260)<br />
Peter Bennett, Barbara Oberlander, Erlend Larsen, Institutt for<br />
Energiteknikk (Norway<br />
21
Tuesday AM Technical Sessions<br />
8. Advanced Surveillance Technologies for Used Fuel Long-<br />
Term Storage and Transportation (wP-59032)<br />
Hanchung Tsai, Yung Liu, Mark Nutt, Argonne National<br />
Laboratory; James Shuler, US Department of Energy (USA)<br />
SESSION 14<br />
Tuesday: 8:30am - 12:30am Room: 5<br />
D&D OF POWER REACTORS AND RESEARCH REACTORS<br />
(3.9)<br />
Co-Chairs: Jean-Marie Cuchet, BELGONUCLEAIRE (Belgium)<br />
Kenneth Kok, ASME (USA)<br />
Organizers: Jean-Marie Cuchet and Jas S. Devgun<br />
1. DfD an Approach to New Reactor Designs (wP-59197)<br />
Jas S. Devgun, Sargent & Lundy (USA)<br />
2. Feedback from Westinghouse Experience on Segmentation<br />
of Reactor Vessel Internals (wP-59013)<br />
Joseph Boucau, Westinghouse Electric Company; Stefan<br />
Fallström, Westinghouse; Per Segerud, Westinghouse Electric<br />
Sweden; Paul Kreitman, Westinghouse Electric Company<br />
(Belgium/Sweden/USA)<br />
3. Update on Jose Cabrera NPP Decommissioning (wP-59322)<br />
Juan Santiago, Nieves Martin, Manuel Rodriguez, ENRESA<br />
(Spain)<br />
4. The Decommissioning of the CIEMAT Nuclear Research<br />
Centre (w/oP-59321)<br />
Juan Santiago, Sergio Vidaechea, Manuel Ondaro, ENRESA<br />
(Spain)<br />
— BREAK —<br />
5. The Removal, Transportation and <strong>Final</strong> Treatment and<br />
Conditioning of the Thetis Research Reactor Spent Fuel of<br />
the University of Ghent (Belgium) Achieved in 2010 Authors<br />
(wP-59261)<br />
Hubert Thierens, Myriam Monsieurs, Ghent University; Vincent<br />
De pooter, Marnix Braeckeveldt, NIRAS/ONDRAF; Luc<br />
Noynaert, SCK●CEN; Patrick Lewandowski, Belgoprocess;<br />
Patrick Maris, Luc Ooms, SCK●CEN; Karel Strijckmans, Ghent<br />
University (Belgium)<br />
6. Decommissioning and Dismantling of the French Brennilis<br />
NPP (w/oP-59366)<br />
Thierry Andre, ONET Technologies; Werner Botzem, Nukem<br />
Technologies (France/Germany)<br />
7. The Chooz a Reactor Dismantling Project (wP-59363)<br />
Estelle Grevin, EDF; Joseph Boucau, Westinghouse Electric<br />
Company (France/Belgium)<br />
8. Full System Decontamination (FSD) Prior to Decommissioning<br />
(wP-59189)<br />
Christoph Stiepani, AREVA NP GmbH (Germany)<br />
SESSION 15<br />
Tuesday: 8:30am - 10:15am Room: 10<br />
THE FRENCH D&D ACTIVITIES - ORGANIZATION,<br />
STRATEGY, OBJECTIVES AND EXPERIENCE (3.2)<br />
Co-Chairs: Jean-Guy Nokhamzon, CEA/DEN/DADN (France)<br />
Jim Marra, US DOE (USA)<br />
Organizer: Jean-Guy Nokhamzon<br />
Reviewers: Jean-Guy Nokhamzon and Andy Szilagyi<br />
1. CEA’s Decommissioning Policy and Strategies. Lessons<br />
Learned (w/oP-59203)<br />
Philippe Guiberteau, Didier Dall’ava, CEA; Jean-Guy<br />
Nokhamzon, CEA/DEN/DADN (France)<br />
2. Cleansing and Dismantling of CEA-Saclay Nuclear Licensed<br />
Facilities (w/oP -59227)<br />
Michel K. Jeanjacques, Rebecca Glévarec, Isabelle Delaire,<br />
Jean Louis Martin, Commissariat à l’Energie Atomique et aux<br />
Energies Alternatives (France)<br />
3. Decontamination and Dismantling of CENDRILLON<br />
Transfer Systems for Radioactive Liquid Solutions (w/oP -<br />
59336)<br />
Michel K. Jeanjacques, Commissariat à l’Energie Atomique et<br />
aux Energies Alternatives; Frédéric Masure, Alternative<br />
Energies and Atomic Energy Commission (France)<br />
22<br />
4. AREVA Return on Experience from D&D <strong>Program</strong>me<br />
Management - What we have Learned so Far? (w/oP -59324)<br />
Jean-Michel Chabeuf, Thierry Varet, Grégoire de Laval, Guy<br />
Decobert, Frédéric Chambon, AREVA Nuclear Site Value<br />
Development BU (France)<br />
SESSION 16<br />
Tuesday: 10:45am - 12:30pm Room: 10<br />
NATIONAL AND INTERNATIONAL D&D PROGRAMS (3.3)<br />
Co-Chairs: Sean Bushart, Electric Power Research Institute (USA)<br />
Thibaud Labalette, Andra (France)<br />
Organizers: Jas Devgun and Thierry Varet<br />
Reviewers: Sean Bushart and Dominique Greneche<br />
1. Particularities of CHNPP Site Remediation During its<br />
Decommissioning (wP-59193)<br />
Sergii Mitichkin, Valeriy Seyda, Chernobyl NPP (Ukraine)<br />
2. Division of Nuclear Liabilities between different License<br />
Holders and Owners (wP-59214)<br />
Staffan Lindskog, Swedísh Radiation Safety Authority; Rolf<br />
Sjöblom, Tekedo AB (Sweden)<br />
3. Spanish Approach to Large Decommissioning Projects (wP-<br />
59320)<br />
Juan Santiago, Alejandro Rodríguez, ENRESA (Spain)<br />
4. Decommissioning of Obsolete Nuclear Facilities in the<br />
Nuclear Research Institute Rez (wP-59309)<br />
Josef Podlaha, Karel Svoboda, Nuclear Research Institute Rez;<br />
Eduard Hanslik, T.G.M. Water Research Institute (Czech<br />
Republic)<br />
SESSION 17<br />
Tuesday: 8:30am - 10:15am Room: 6<br />
APPLYING STRATEGIC PLANNING, DECISION-MAKING<br />
AND RISK REDUCTION METHODOLOGIES IN EM (5.7)<br />
Co-Chairs: Mark Nutt, ANL (USA)<br />
Dominique Francois-Bongarcon,<br />
AGORATEK International Consultants (Canada)<br />
Organizer: Roger Seitz<br />
Reviewers: Roger Seitz and Dominique Francois-Bongarcon<br />
1. Can Sustainability be Applied to our Environmental<br />
Remediation Challenges? (w/oP-59148)<br />
Peter Booth, Vicky Gaskin, WSP Environment and Energy (UK)<br />
2. Evolution of Performance Assessment Modeling in the US<br />
(w/oP- 59334)<br />
Paul Black, John Tauxe, Neptune and Company, Inc. (USA)<br />
SESSION 18<br />
Tuesday: 10:45am - 12:30pm Room: 6<br />
ECONOMIC ANALYSES, MONITORING STRATEGIES AND<br />
PROJECT MANAGEMENT IN ENVIRONMENTAL<br />
MANAGEMENT (5.6)<br />
Co-Chairs: Yvette Collazo, US DOE (USA)<br />
Paul Black, Neptune and Company, Inc. (USA)<br />
Organizers: Judy Connell and Yvette Collazo<br />
Reviewers: Yvette Collazo and Paul Black<br />
1. Delivering Value for Money - Trust and Verify? (wP-59253)<br />
Alastair Laird, Project Time & Cost Inc. (USA)<br />
2. The Technical and Economical Optimization of the French<br />
Geological Repository Project (w/oP-59275)<br />
Rodolphe Raffard, Thibaud Labalette, Andra (France)<br />
3. The Environmental Monitoring System Developed within<br />
the Framework of the French Radioactive Waste Deep<br />
Repository Project (w/oP-59296)<br />
Elisabeth Leclerc; Patrick Landais, Andra (France)
Technical Sessions Tuesday PM<br />
SESSION 19<br />
Tuesday: 12:00pm-6:00pm Room: Exhibit Hall<br />
POSTER SESSION: SPENT FUEL, FISSILE, TRANSURANIC<br />
AND HIGH LEVEL WASTE MANAGEMENT (2.1)<br />
Co-Chairs: Ed Bentz, E.J. Bentz & Associates (USA)<br />
Heather Klebba, NFT (USA)<br />
Reviewers: Heather Klebba, Gerald Ouzounian, and Ed Bentz<br />
1. ADONIS, High Count Rate Hp-Ge ƴ Spectrometry<br />
Algorithm: Irradiated Fuel Assembly Measurement<br />
(wP-59234)<br />
Patrick Pin, AREVA NC; Eric Barat, Thomas Dautremer,<br />
Thierry Montagu, Stéphane Normand, CEA - Saclay (France)<br />
2. Technical Know-How for the Investigation and Modelling of<br />
Topographic Evolution for Site Characterisation<br />
(wP-59171)<br />
Ryosuke Doke, Ken-ichi Yasue, Tadafumi Niizato, Akio<br />
Nakayasu, Japan Atomic Energy Agency (Japan)<br />
3. Validation of Correlations between ND Isotopes and<br />
Difficult-To-Measure Nuclides Predicted with Burn-Up<br />
Calculation Code By Post Irradiation Examination<br />
(wP-59086)<br />
Shiho Asai, Keisuke Okumura, Yukiko Hanzawa, Hideya Suzuki,<br />
Masaaki Toshimitsu, Jun Inagawa, Takaumi Kimura, Japan<br />
Atomic Energy Agency; Satoru Kaneko, Kensuke Suzuki, Tokyo<br />
Electric Power Company (Japan)<br />
4. Computational Study for Inventory Estimation of Se-79, Tc-<br />
99, Sn-126, and Cs-135 in High-Level Radioactive Wastes<br />
from Spent Nuclear Fuels of Light Water Reactors<br />
(wP-59087)<br />
Keisuke Okumura, Shiho Asai, Yukiko Hanzawa, Tsutomu<br />
Okamoto, Hideya Suzuki, Masaaki Toshimitsu, Jun Inagawa,<br />
Takaumi Kimura, Japan Atomic Energy Agency; Satoru Kaneko,<br />
Kensuke Suzuki, Tokyo Electric Power Company (Japan)<br />
5. Industrial Scale HL-LL Waste Canister Transfer<br />
Demonstrator (wP-59305)<br />
Pascal Champ, Jacques Bardet, Benjamin Attias, Cegelec<br />
(France)<br />
6. CESAR5.3: An Industrial Tool for Irradiated Nuclear Fuel<br />
and Waste Characterisation, with an Associated<br />
Qualification (w/oP-59080)<br />
Jean-Marc Vidal, Romain Eschbach, Commissariat à lÉnergie<br />
Atomique et aux Énergies Alternatives; Agnes Launay,<br />
Christophe Binet, AREVA_NC (France)<br />
7. Test Procedure with a 15,000 kg half-scale Prototype of<br />
Transport and Storage Cask (w/oP-59141)<br />
Andre Musolff, Thomas Quercetti, Karsten Müller, BAM -<br />
Federal Institute for Materials Research and Testing (Germany)<br />
8. Capillary Electrophoresis with Laser-Induced Fluorescent<br />
Detection Method Using Highly Emissive Probes for Analysis<br />
of Actinides in Radioactive Wastes (wP-59092)<br />
Tomoko Haraga, Japan Atomic Energy Agency; Yuta Nakano,<br />
Masami Shibukawa, Saitama University; Yutaka Kameo,<br />
Kuniaki Takahashi, Japan Atomic Energy Agency; Shingo Saito,<br />
Saitama University (Japan)<br />
9. A New Way of Eliminating Tributylphosphate and Dodecane<br />
Mixtures Using Advanced Oxidation Techniques<br />
(w/oP-59104)<br />
Geraldine Dupuy, DEWDROPS (France)<br />
10. The FP7 Collaborative Project ReCosy (w/oP-59397)<br />
Gunnar Buckau, Institute for Transuranium Elements, Joint<br />
Research Center, European Union; Anne Delos, Vanessa<br />
Montoya, Amphos 21 (Germany/France/Spain)<br />
11. Technical Know-How of Site Descriptive Modeling for Site<br />
Characterization (wP-59089)<br />
Hiromitsu Saegusa, Tadafumi Niizato, Ken-ichi Yasue, Hironori<br />
Onoe, Ryosuke Doke, Japan Atomic Energy Agency (Japan)<br />
12. A Comprehensive Information Management System for<br />
European Disposal R&D (INMAN): A Proposal for the Next<br />
European Framework <strong>Program</strong> (w/oP-59397)<br />
Gunnar Buckau, Institute for Transuranium Elements, Joint<br />
Research Center, European Union; Anne Delos,Vanessa<br />
Montoya, Amphos 21 (Germany/France/Spain)<br />
13. Development of Comprehensive Techniques for Coastal Site<br />
Characterization: Integrated Palaeohydrogeological<br />
Approach for Development of Site Evolution Models<br />
(wP-59259)<br />
Kenji Amano, Tadafumi Niizato, Kunio Ota, Japan Atomic<br />
Energy Agency; Bill Lanyon, Nagra; W Russell Alexander,<br />
Bedrock Geosciences (Japan/Switzerland)<br />
SESSION 20<br />
Tuesday: 1:45pm - 6:00pm Room: 1<br />
PANEL: CHALLENGES WHEN SELECTING DISPOSAL<br />
OPTIONS IN THE LIGHT OF THE NEW IAEA<br />
CLASSIFICATION SCHEME (1.17)<br />
Co-Chairs: Angie Jones, AMEC (USA)<br />
Peter Ormai, IAEA (Austria)<br />
Organizer: Peter Ormai<br />
The new IAEA classification scheme is based on long term safety –<br />
primarily disposal. The potential options for disposal include: above<br />
surface engineered landfill, near surface disposal (trenches, vaults or<br />
shallow boreholes), engineered facilities at intermediate depth (10s to<br />
100s of meters) and geological disposal (> few hundred metres).<br />
Specific waste types will need specific consideration (e.g. disused<br />
sealed sources, graphite waste, and radium bearing waste). National<br />
schemes will be circumstance dependent.<br />
The following will be discussed:<br />
• Near surface or geological disposal for SL-LILW<br />
• Separate disposal for SL-LILW and VLLW<br />
• Advantages and disadvantages of opting for co-disposal<br />
• Borehole disposal as potential solution for the countries having<br />
limited waste inventories<br />
• Feasible approaches for disposal of low level long-lived waste<br />
This panel will provide a forum for the exchange of scientific and<br />
technical information on disposal of different categories of radioactive<br />
waste with focus on current approaches.<br />
Panelists include: Linde Nel, Director of Operations and<br />
Maintenance Services (South Africa); Vaclav Hanusik, Senior<br />
Researcher, VUJE (Slovak Republic); Dr. Irina Gaus, Senior Expert<br />
(Switzerland); Thibaud Labalette, <strong>Program</strong> Director at Andra<br />
(France); Balint Nos, Head of Strategy Development and<br />
Engineering Office of PURAM (Hungary); Dr. Peter Brennecke,<br />
Bundestamt fur Strahlenschutz (BFS), Retired (Germany); Dr.<br />
Kazumi Kitayama, Senior Technical Advisor, Nuclear Waste<br />
Management Organization of Japan (NUMO) (Japan); and Keith<br />
McConnell, Deputy Director, US NRC (USA)<br />
SESSION 21<br />
Tuesday: 1:45pm-3:30pm Room: 4<br />
PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF<br />
INTERIM STORAGE, GEOLOGICAL DISPOSAL,<br />
PARTITIONING & TRANSMUTATION REVERSIBILITY<br />
REGARDING GLOBAL OPTIMIZATION OF RADWASTE<br />
MANAGEMENT (2.15)<br />
Co-Chairs: Jean-Michel Hoorelbeke, Andra (France)<br />
Heather Klebba, NFT (USA)<br />
Organizer: Jean-Michel Hoorelbeke<br />
Session 21 is a two part panel in conjunction with Session 22. The<br />
first part will consist of a introductory paper and then a panel will<br />
address the status of HLW and Spent Fuel interim storage, processing<br />
and national programs. Partitioning and transmutation are also<br />
investigated in several countries. Interim storage is required to<br />
accommodate waste as long as sustainable management solutions are<br />
not available and interim storage duration up to 100 years has been<br />
often considered.<br />
Panelists include: Bernard Boullis, CEA (France); Wilhelm<br />
Bollingerfehr, DBE (Germany); Philippe Lallieux ONDRAF<br />
(Belgium); Claudio Pescatore, NEA, (France); Jean-Michel<br />
Hoorelbeke, Andra (France); Farok Sharif, URS (USA); Jürg<br />
Schneider, NAGRA (Switzerland); and Neil Smart, NDA (UK)<br />
23
Tuesday PM Technical Sessions<br />
1. New Nuclear <strong>Program</strong>mes Must Not Neglect Waste<br />
Management (wP-59077)<br />
Charles McCombie, Arius Association (Switzerland)<br />
SESSION 22<br />
Tuesday: 4:15pm-6:00pm Room: 4<br />
PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF<br />
INTERIM STORAGE, GEOLOGICAL DISPOSAL,<br />
PARTITIONING & TRANSMUTATION REVERSIBILITY<br />
REGARDING GLOBAL OPTIMIZATION OF RADWASTE<br />
MANAGEMENT (2.15)<br />
Co-Chairs: Jean-Michel Hoorelbeke, Andra (France)<br />
Heather Klebba, NFT (USA)<br />
Organizer: Jean-Michel Hoorelbeke<br />
Session 22, the second part of this two part panel will discuss final<br />
disposition and geological disposal issues since it is internationally<br />
recognized as the reference option for long term management of high<br />
level and TRU waste, or non reprocessed spent fuel. Nevertheless the<br />
progress of geological repositories varies significantly from one<br />
country to another. In many cases some reversibility or irretrievability<br />
is expected by stakeholders.<br />
Specialists know that geological repository will not suppress the need<br />
for interim storage, and that partitioning and transmutation cannot<br />
suppress the need for geological disposal. The panel will discuss the<br />
potential complementarities of these various waste management tools,<br />
or their incompatibilities if any, with regard to possible optimization<br />
of the whole system. Different time scales and types of waste will be<br />
considered as necessary.<br />
Panelists include: Bernard Boullis, CEA (France); Wilhelm<br />
Bollingerfehr, DBE (Germany); Philippe Lallieux ONDRAF<br />
(Belgium); Claudio Pescatore, NEA, France; Jean-Michel<br />
Hoorelbeke, Andra (France); Farok Sharif, URS (USA); Jürg<br />
Schneider, NAGRA (Switzerland); and Neil Smart, NDA (UK)<br />
SESSION 23<br />
Tuesday: 1:45pm-3:30pm Room: 2<br />
ADVANCED L/ILW CONDITIONING TECHNOLOGIES -<br />
PART 1 OF 2 (1.11)<br />
Co-Chairs: Mike Garamszeghy, Nuclear Waste Management<br />
Organization (Canada)<br />
Andrew Baker, Eden Nuclear and Environment<br />
Ltd. (UK)<br />
Organizer: Angie Jones<br />
Reviewers: Mike Garamszeghy and Andrew Baker<br />
1. Cementitious Materials for Radioactive Waste Management<br />
Within IAEA Coordinated Research Project (wP-59021)<br />
Zoran Drace, IAEA; Michael Ojovan, University of Sheffield<br />
(Austria/UK)<br />
2. Elution Behavior of Heavy Metals from Cement Solidified<br />
Products of Incinerated Ash Waste (wP-59102)<br />
Yoshihiro Meguro, Yoshimi Kawato, Takuya Nakayama,Osamu<br />
Tomioka, Motoyuki Mitsuda, Japan Atomic Energy Agency<br />
(Japan)<br />
3. Immobilisation of Radwaste in Synthetic Rock: An<br />
Alternative to Cementation (W/P-59008)<br />
Bernard Rottner, Onet Technologies (France)<br />
24<br />
SESSION 24<br />
Tuesday: 4:15-6:00pm Room: 2<br />
L/ILW WASTE CHARACTERIZATION, ASSAY, AND<br />
TRACKING SYSTEMS - PART 1 OF 2 (1.7)<br />
Co-Chairs: Jeffrey Lively, AMEC (USA)<br />
Jerome Brueziere, AREVA (France)<br />
Organizers: Ronald Keyser and Karan North<br />
Reviewers: Karan North and Jerome Brueziere<br />
1. A Proposed Figure of Merit for Evaluating the Performance<br />
of Radiation Identification and Detection Systems<br />
(wP-59159)<br />
Ronald Keyser, Timothy Twomey, ORTEC - AMETEK; Michael<br />
D. Belbot, Thermo Fisher Scientific; Neil Andrew Webster,<br />
Thermo Fisher Scientific, Radiation Measurement & Security<br />
Instruments (USA)<br />
2. Characterization of Legacy Low Level Waste at the SVAFO<br />
Facility Using Gamma Non-Destructive Assay and X-Ray<br />
Non-Destructive Examination Techniques (wP-59289)<br />
Stephen Halliwell, VJ Technologies Inc; Gary Mottershead, VJ<br />
Technologies Inc; Fredrik Ekenborg (USA/France/Sweden)<br />
3. Calibration and Validation of a Wide Range Segmented<br />
Gamma Ray Scanning Instruments for the Measurement of<br />
Low and Intermediate Level Waste (wP-59304)<br />
John Mason, A. N. Technology Ltd.; Kapila Fernando, ANSTO,<br />
Australia Nuclear Science and Technology Organization<br />
(UK/Australia)<br />
4. Performance of a DrumScan® HRGS Solo Scanner for the<br />
Assay of Legacy Waste at the Belgoprocess Site (wP-59122)<br />
Daniel Parvin, Babcock International Group; Thomas Huys,<br />
Belgoprocess, Dessel, (UK/Belgium)<br />
SESSION 25<br />
Tuesday: 1:45-6:00pm Room: 3<br />
D&D OF NON-REACTOR NUCLEAR FACILITIES (3.10)<br />
Co-Chairs: Kenneth Kok, ASME (USA)<br />
Lucien Pillette-Cousin, Areva (France)<br />
Organizers: Jas Devgun and Jean-Guy Nokhamcon<br />
Reviewers: Ken Kok and Lucien Pillette-Cousin<br />
1. Decommissioning The Belgonucleaire Dessel Mox Plant:<br />
Presentation of The Project And Situation on 30/06/2011<br />
(wP-59027)<br />
Jean-Marie Cuchet, Carlo Verheyen, Henri Libon,<br />
Belgonucleaire; Jos Custers, Tecnubel; Robert Walthery,<br />
Belgoprocess; Jozef Bily, Studsvik (Germany)<br />
2. Uranium Workshops Dismantling and Criticality Control<br />
(wP-59060)<br />
Pierre Lisbonne, Julie Rosello, CEA (France)<br />
3. The Complex Challenge of Refurbishing the Pond Gantry<br />
Steelwork which Supports the Pond Skip Handler above the<br />
First Generation Magnox Storage Pond at Sellafield (wP-<br />
59133)<br />
Ian Richardson, Sellafield (UK)<br />
4. Systematic Chemical Decontamination Using IF7 Gas<br />
(wP-59036)<br />
Haruhi Hata, Kaoru Yokoyama, Noritake Sugitsue, Japan<br />
Atomic Energy Agency (Japan)<br />
— BREAK —<br />
5. Decommissioning & Demolition of Facilities used for the<br />
Storage & Stabilisation of Water Reactor Sludge (wP-59097)<br />
Nicholas J. Brown, Rowland Cornell, Nuvia Limited; Andy<br />
Staples, RSRL (UK)<br />
6. Decommissioning of the Radio Chemical Hot Laboratory of<br />
the European Commission Joint Research Centre of ISPRA<br />
(wP-59207)<br />
Daniele Ugolini, Francesco Rossi, Francesco Basile, European<br />
Commission Joint Research Centre (Italy)<br />
7. A Successful Transition from Operating to Dismantling a<br />
UO2-PuO2 Fuel Fabrication Facility (w/oP-59326)<br />
Thierry Flament, AREVA NC (France)
Technical Sessions Tuesday PM<br />
SESSION 26<br />
Tuesday: 1:45pm-6:00pm Room: 5<br />
D&D TECHNOLOGIES - PART 1 OF 2 (3.4)<br />
Co-Chairs: Jas Devgun, Sargent & Lundy (USA)<br />
Jean-Guy Nokhamzon, CEA/DEN/DADN<br />
(France)<br />
Organizer/Reviewer: Jas Devgun<br />
1. Dismantling/Remediation of a Highly Contaminated Sump<br />
in Running Plant Conditions (w/oP-59053)<br />
Jos Boussu, Koen Lenie, Tecnubel (Belgium)<br />
2. New Degreasing Formulations for the Decontamination of<br />
Solid Substrates, Consistent with Vitrification Process of the<br />
<strong>Final</strong> Wastes (w/oP-59166)<br />
Jeremy Causse, Cyril Roussignol, French Atomic Enrgy<br />
Commission; Jean-François Valery, Jean Charles Hamel, Areva<br />
NC (France)<br />
3. The Orion ScanSort Soil Sorting System (w/oP-59385)<br />
Jeffrey Lively, MACTEC (USA)<br />
4. Liquids, Gels, Foams and Supercritical Fluids: Four States<br />
of Matter for Radioactive Decontamination of Solids<br />
(w/oP-59158)<br />
Sylvain Faure, Jérémy Causse, Bruno Fournel, CEA (France)<br />
— BREAK —<br />
5. Decommissioning of the A-1 NPP Heavy Water Evaporator<br />
Facility (wP-59225)<br />
Jan Medved, VUJE Inc.; Ladislav Vargovcik, ZTS VVU Kosice<br />
a.s. (Slovakia)<br />
6. Remote Decommissioning of Blind Cells - APM 214 Facility<br />
CEA Marcoule (w/oP-59206)<br />
Olivier Calixte, ONET Technologies - ONECTRA (France)<br />
7. Transport of Nuclear Waste Flows - A Modeling and<br />
Simulation Approach (wP-59136)<br />
Jonathan Adams, Michael Fairweather, James Young, Simon<br />
Biggs, Jun Yao, University of Leeds, Leeds (UK)<br />
8. Fuel Racks Dismantling Workshop at CENTRACO Facility<br />
(wP-59365)<br />
Jean-François Rives, Christophe Maufrais, SOCODEI (France)<br />
SESSION 27<br />
Tuesday: 1:45pm-6:00pm Room: 10<br />
ER SITE CHARACTERIZATION AND MONITORING - PART<br />
1 OF 2 (4.5)<br />
Co-Chairs: Nicolas Jeannée, GEOVARIANCES (France)<br />
Virgene Mulligan, ARS International, Inc. (USA)<br />
Organizers: Steve Brown and Didier Dubot<br />
Reviewers: Nicolas Jeannée and Virgene Mulligan<br />
1. Soils Radiological Characterization Under a Nuclear Facility<br />
(wP-59046)<br />
Emilie Aubonnet, Geovariances / CEA FAR, Fontenay aux<br />
Roses, France, Didier Dubot, CEA/FAR/USLT/SPRE/SAS,<br />
Fontenay aux Roses (France)<br />
2. Radiological Evaluation of Contaminated Sites and Soils<br />
VEGAS: An Expertise and Investigating Vehicle (wP-59057)<br />
Julien Attiogbe, GEOVARIANCES; Marie Lavielle, Patrick De<br />
Moura, CEA (France)<br />
3. Determination of the Radionuclide Contamination on the<br />
Absheron Peninsula in Azerbaijan (wP-59177)<br />
Tjalle Vandergraaf, Providence University College; Gudrat G<br />
Mamedov, Mahammadali A. Ramazanov, Baku State University;<br />
Jalal A. Naghiyev, Institute of Radiation Problems; Afat A.<br />
Mehdiyeva, National Aerospace Agency of Azerbaijan; Nazim A.<br />
Huseynov, Institute of Radiation Problems (Canada/Azerbaijan)<br />
4. High-density Gamma Radiation Spectrometry Surveys of<br />
Contaminated Land (wP-59076)<br />
Mike Davies, Robert Clark, Ian Adsley, Nuvia Limited (UK)<br />
— BREAK —<br />
5. Remediation and Assessment of the National Radioactive<br />
Waste Storage and Disposal Site in Tajikistan (wP-59110)<br />
Nazirzhon Buriev, Dzhamshed Abdushukurov, Physical-<br />
Technical Institute of the Academy of Sciences of the Republic of<br />
Tajikistan; Tjalle Vandergraaf, Providence University College<br />
(Tajikistan/Canada)<br />
6. Integrating History and Measurement into a Case for Site<br />
Release (wP-59131)<br />
Angela Bartlett, Research Sites Restoration Limited; Mike<br />
Davies, Pete Burgess, Nuvia Ltd; Gavin Coppins, Babcock<br />
International Group (UK)<br />
7. Characterization of a Deep Radiological Contamination:<br />
Integration of Geostatistical Processing and Historical Data<br />
(wP-59062)<br />
Yvon Desnoyers, GEOVARIANCES; Patrick De Moura, CEA<br />
(France)<br />
8. Industrial Experience Feedback of a Geostatistical<br />
Estimation of Contaminated Soil Volumes (wP-59181)<br />
Claire Faucheux, Nicolas Jeannée, GEOVARIANCES(France)<br />
SESSION 28<br />
Tuesday: 1:45pm - 6:00pm Room: 6<br />
PUBLIC PERCEPTION ISSUES AND STAKEHOLDER<br />
ENGAGEMENT STRATEGIES IN RADIOACTIVE<br />
ENVIRONMENTAL MANAGEMENT (5.5)<br />
Co-Chairs: Judy Connell, Fluor Government Group (USA)<br />
Sebastien Farin, Andra (France)<br />
Organizer: Judy Connell<br />
Reviewers: Judy Connell and Sebastien Farin<br />
1. Perspectives on Reversibility and Retrievability of a<br />
Geological Repository in France (wP - 59263)<br />
Jean-Noel Dumont, Jean-Michel Hoorelbeke, Andra (France)<br />
2. A Dialogue-Centric Approach to Environmental<br />
Remediation Decision-Making (wP -59115)<br />
Laurel Boucher, The Laurel Co.; James Clark, CRX Group, Inc.<br />
(USA)<br />
3. Outreach and Education - Ensuring a Clean Energy Future<br />
for All (wP - 59339)<br />
Susan Hess, Areva Inc USA)<br />
4. Challenge in the Public Acceptance and Cooperation in the<br />
Verge of Building the First Nuclear Power Plant in Indonesia<br />
(wP - 59119)<br />
Putero Susetyo Hario, Santosa Haryono Budi, Gadjah Mada<br />
University (Indonesia)<br />
— BREAK —<br />
5. Andra Long Term Memory Project (wP - 59277)<br />
Patrick Charton, Fabrice Boissier, Guillaume Martin, Andra<br />
(France)<br />
6. Engaging Local Stakeholders on Technical Issues: Test Case<br />
at the La Hague Reprocessing Plant (wP - 59211)<br />
Ludivine Gilli, Institut de radioprotection et de sûreténucléaire<br />
(IRSN) (France)<br />
7. Creating and Managing Radioactive Waste Disposal<br />
Facilities with the Involvement of the Local Populations<br />
(w/oP - 59286)<br />
Sébastien Farin, Andra (France)<br />
SESSION 29<br />
Wednesday: 8:30am-12:30pm Room: 1<br />
PANEL: INTERNATIONAL COOPERATION: NEA ROAD<br />
MAP, HOW TO INCREASE SYNERGY (3.12)<br />
Co-Chairs: Hans Riotte, OECD/NEA (France)<br />
Jean-Guy Nokhamzon, CEA/DEN/DADN<br />
(France)<br />
Organizers: Hans Riotte and Jean-Guy Nokhamzon<br />
This session will start with short presentations and conclude with a<br />
panel session. The presentations will include;<br />
1. Recent Work And Achievements At The Nuclear Energy<br />
Agency InDecommissioning: Claudio Pescatore (OECD/NEA)<br />
25
Wednesday AM Technical Sessions<br />
2. Cooperative <strong>Program</strong> on Dismantling and Decommissioning<br />
(CPD) -Overview, Jan Carlson & Jean-Guy Nokhamzon<br />
3. CPD - Decontamination and Dismantling of Concrete<br />
Structures, Eric Cantrel (CEN/SCK/Mol)<br />
4. CPD -Experience with Remote Handling Techniques, Pierre<br />
Valentin (CEA/DEN/DPAD)<br />
5. Working Party on Dismantling and Decommissioning<br />
(WPDD) - Overview, Ivo Tripputi (Sogin)<br />
— BREAK —<br />
6. WPDD -Integration of Waste Management and<br />
Decommissioning: The Management of Large Components,<br />
Michel Dutzer (Andra)<br />
7. WPDD -Decommissioning Techniques: Prospects for R &D,<br />
Gerard Laurent (EDF/CIDEN)<br />
8. WPDD -Decommissioning Costs: Yellow book and Cost<br />
Control, Patrick Devaux (CEA/DEN/DPAD)<br />
9. WPDD -Decommissioning Feedback for New Nuclear Power<br />
Plants, Rateb Abu-Eid (US/NRC)<br />
The session will end with a panel discussions moderated by Ivo<br />
Tripputi (Sogin).<br />
Panelists include: Juan Luis Santiago (Enresa), Jim Marra (US<br />
DOE), and Gerard Laurent (EDF/CIDEN)<br />
SESSION 30<br />
Wednesday: 8:30am - 12:30pm Room: 2<br />
SITING, DESIGN, CONSTRUCTION, AND OPERATION OF<br />
L/ILW DISPOSAL FACILITIES - PART 1 OF 2 (1.12)<br />
Co-Chairs: Philip Rendell, NDA (UK)<br />
Patrice Torres, Andra (France)<br />
Organizers/Reviewers: Cathy Hickey and Philip Rendell<br />
1. An Innovative Design for Low and Intermediate Radwaste<br />
Near Surface Repository in Lithuania (w/oP-59382)<br />
Boniface Jean-Michel, AREVA TA (France)<br />
2. Product Quality Control of Radioactive Waste with a Special<br />
Regard to Federal States Collecting Facilities (w/oP-59176)<br />
Markus Havertz, Research Centre Jülich GmbH (Germany)<br />
3. Centre de la Manche: A Disposal Facility in Institutional<br />
Control (wP-59236)<br />
Michel Dutzer, Jean Pierre Vervialle, Alain André, Albert<br />
Marchiol, Andra (France)<br />
4. Radiological Impact of Co-Location of the VLLW and LILW<br />
Repository at Mochovce site (wP-59152)<br />
Václav Hanusík, Zdena Kusovská, Jozef Morávek, VUJE, Inc.;<br />
J. Balaz, O. Chren, Nuclear and Decommissioning Company<br />
plc. (Slovakia)<br />
— BREAK —<br />
5. Development of an Engineering Design Process and<br />
Associated Systems and Procedures for a UK Geological<br />
Disposal Facility (wP-59160)<br />
Philip Rendell, NDA; Henry O’Grady, Parsons Brinckerhoff:<br />
Brendan Breen, Alastair Clark, Steve Reece, NDA (UK)<br />
6. State of the Art for Fabricating and Emplacing Concrete<br />
Containers into Large Horizontal Disposal Caverns in the<br />
French Geological Repository (wP-59267)<br />
Jean-Michel Bosgiraud, Maurice Guariso, François Pineau,<br />
Andra (France)<br />
7. On-Site, Near Surface Disposal of Graphite Wastes in the<br />
UK (wP-59078)<br />
Adam Meehan, Peter Sibley, EnergySolutions; Jeremy<br />
Lightfoot, Golder Associates (UK) Ltd.; Duncan Jackson, Eden<br />
Nuclear & Environment Ltd., (UK)<br />
26<br />
SESSION 31<br />
Wednesday: 8:30am - 12:30pm Room: 3<br />
L/ILW WASTE CHARACTERIZATION, ASSAY, AND<br />
TRACKING SYSTEMS - PART 2 OF 2 (1.18)<br />
Co-Chairs: Ronald Keyser, ORTEC - AMETEK (USA)<br />
Jerome Brueziere, AREVA (France)<br />
Organizers: Ronald Keyser and Karan North<br />
Reviewers: Ronald Keyser and Jerome Brueziere<br />
1. Non-Destructive Examination of TRU Waste in Low and<br />
High Density Boxes and Drums, using High Energy Real<br />
Time Radioscopy (HE-RTR) and Wide Dynamic Range<br />
Imaging (wP-59302)<br />
Stephen Halliwell, VJ Technologies Inc. (USA)<br />
2. Measurement Methodology for Fulfilling of Waste<br />
Acceptance Criteria for Low and Intermediate Level<br />
Radioactive Waste in Storages (wP-59016)<br />
Marina Sokcic-Kostic, Felix Langer, Roland Schultheis,<br />
NUKEM Technologies GmbH (Germany)<br />
3. Disposition of Transuranic Residues from Plutonium<br />
Isentropic Compression Experiment (Pu-ICE) conducted at<br />
Z Machine (LA-UR-10-05649) (wP-59186)<br />
Kapil K. Goyal, Los Alamos National Laboratory; Betty J.<br />
Humphrey, Weston Solutions Inc.; Jeffry Gluth, Ktech<br />
Corporation/Sandia National Laboratory; David M. French,<br />
Los Alamos National Laboratory (USA)<br />
4. Detection of Shielded Sealed Radioactive Sources in<br />
Radioactive Waste by Non-Destructive Assay Techniques<br />
(wP-59252)<br />
Leo P.M. Velzen, Nuclear Research and Consultancy Group;<br />
Steven van der Marck, Nuclear Research Group (Netherlands)<br />
— BREAK —<br />
5. Use of Lanthanum Bromide Detectors to Augment Site<br />
Surveys for Depleted Uranium (w/P-59169)<br />
Charles Waggoner, Mississippi State University; Ronald Unz,<br />
Institute for Clean Energy Technology; Donna Rogers,<br />
Mississippi State University; Charles R. Jones, Jay P. McCown,<br />
Institute for Clean Energy Technology/Mississippi State<br />
University (USA)<br />
6. Ultrasonic Techniques for the In Situ Characterisation of<br />
‘Legacy’ Waste Sludges & Dispersions (wP-59111)<br />
Timothy Hunter, Jeff Peakall, Simon Biggs, Michael<br />
Fairweather, James Young, University of Leeds, Leeds (UK)<br />
7. Free-Release and Sorting Monitors Developed for NPP A-1<br />
Decommissioning, Slovakia (wP-59071)<br />
Ondrej Slávik, VUJE; Alojz Slaninka, VUJE, a.s./ Slovak<br />
University of Technology in Bratislava; Martin Liatjak, Kamil<br />
Kravárik, VUJE, a.s.; Igor Pély, JAVYS, a.s. (Slovakia)<br />
8. Design and Operation of the Combined Technology<br />
Automated Waste Characterisation System (wP- 59308)<br />
John Mason, Marc R Looman, Robert A. Price, A. N.<br />
Technology Ltd. (UK)<br />
SESSION 32<br />
Wednesday: 8:30am - 12:30pm Room: 4<br />
REPOSITORY PROGRAMS: SITE SELECTION &<br />
CHARACTERIZATION, UNDERGROUND RESEARCH LABS,<br />
ENGINEERING & GEOLOGICAL BARRIERS - PART 1 OF 2<br />
(2.3)<br />
Co-Chairs: Irina Gaus, Nagra (Switzerland)<br />
Jean Paul Chiles, Ecole Mines (France)<br />
Organizers: Irina Gaus and Johan Andersson<br />
Reviewers: Irina Guas and Jean-Paul Chiles<br />
1. Safety Assessment Input to Site Selection - The Swedish<br />
Example (wP-59031)<br />
Johan Andersson, JA Streamflow AB (Sweden)<br />
2. Technical Know-How of Selection Process for the Horonobe<br />
Underground Research Laboratory Area and Site<br />
(wP-59088)<br />
Takanori Kunimaru, Ryuji Takeuchi, Tatsuji Matsuzaki, Japan<br />
Atomic Energy Agency (Japan)
Technical Sessions Wednesday AM<br />
3. Characterisation of Bedrock Hydrogeology at the Olkiluoto<br />
Site Using Surface Based and Underground Data<br />
(w/oP-59095)<br />
Lee Hartley, Dave Swan, Steven Baxter, SERCO (UK)<br />
4. Self-Disposal Option for Heat-Generating Waste (wP-59182)<br />
Michael Ojovan, University of Sheffield; Pavel Poluektov,<br />
Vladimir Kascheev, A.A. Bochvar’s VNIINM (UK/Russia)<br />
— BREAK —<br />
5. NUMOs Approach for Long-term Safety Assessment<br />
(wP-59404)<br />
Takeshi Ebashi, Kenichi Kaku, Katsuhiko Ishiguro, Nuclear<br />
Waste Management Organization of Japan (NUMO) (Japan)<br />
6. Modeling Approaches for Evaluating the Effect of<br />
Heterogeneity on Two-Phase Flow Associated with the<br />
Migration of Waste-Generated Gas from SF/HLW- and<br />
L/ILW Repositories in Low-Permeability Formations (wP-<br />
59196)<br />
Alexandros Papafotiou, Rainer Senger, Intera Inc. Swiss<br />
Branch; Andrés Alcolea, TK Consult AG; William Lanyon,<br />
Fracture-Systems Ltd; John Ewing, Intera Inc. Swiss Branch<br />
(Switzerland/UK)<br />
7. A New Safety Concept for Geological Disposal in Japan (II)<br />
(wP-59357)<br />
Kazumi Kitayama, Nuclear Waste Management Organization of<br />
Japan (NUMO) (Japan)<br />
8. Thermo-Hydro-Mechanical Simulation of a Heating and<br />
Hydration Experimental Study (China-Mock-Up) in<br />
Unsaturated GMZ Bentonite (wP-59212)<br />
Liang Chen, Ju Wang, Yuemiao Liu, Beijing Research Institute<br />
Of Uranium Geology; Federic Collin, University Of Liège;<br />
Jingli Xie, Beijing Research Institute Of Uranium Geology<br />
(China/Belgium)<br />
SESSION 33<br />
Wednesday: 8:30 - 10:15 Room: 6<br />
RECENT ADVANCES IN PROCESSING AND<br />
IMMBOLIZATION OF HLW, FISSLE MATERIAL AND<br />
TRANSUANIC (TRU) - PART 1 OF 2 (2.14)<br />
Co-Chairs: Mark Denton, Kurion Inc. (USA)<br />
Bernard Vigreux, SFEN (France)<br />
Organizers: Mark Denton and Bill Wilmarth<br />
Reviewers: Mark Denton and Bernard Vigreux<br />
1. Uranium Metal Oxidation, Grinding and Encapsulation in<br />
BoroBond: TRU Waste Management (w/oP-59279)<br />
Kevin Cook, Larry Addington, Beth Utley, Boron Products<br />
(USA)<br />
2. Results of Investigation of High Level Solid Radioactive<br />
Waste from Pits No1 and No2 at the Gremikha Site<br />
(w/oP-59390)<br />
B.S. Stepennov, V.M. Afanasyev, A.Yu. Kazennov, N.V. Kartashev,<br />
A.V. Korolev, O.E. Kiknadze, D.V. Pavlov, Kurchatov Institute;<br />
V.V. Eremenko, FGUP SevRAO; G. Fady, CEA; Lucien Pillette-<br />
Cousin, Areva TA (Russia/France)<br />
3. Pilot Test of Precipitation Setup for Dust Supressor and<br />
Transuranic Elements Removal from Wastewaters of<br />
Chernobyl Nuclear Power Plant (w/oP-59256)<br />
Valentin Avramenko, Svetlana Bratskaya, Dmitry Marinin,<br />
Institute of Chemistry FEBRAS; Anatoliy Terzi, Mariya<br />
Yarmolyuk, Chernobyl Nuclear Power Plant (Russia/Ukraine)<br />
4. Separation Processes for the Pretreatment of High-Level<br />
Nuclear Wastes at the Savannah River Site (w/oP-59291)<br />
David Hobbs, Aiken, Thomas Peters, Kathryn Taylor-Pashow,<br />
Fernando Fondeur, Charles Nash, Samuel Fink, David Herman,<br />
Savannah River National Laboratory (SRNL) (USA)<br />
Presentation by: Jim Marra, US DOE (USA)<br />
SESSION 34<br />
(MERGED WITH SESSION 35)<br />
Wednesday: 8:30am - 10:15am Room: 10<br />
URANIUM SITES, ER ISSUES, SITE CHARACTERIZATION<br />
AND MONITORING - PART 2 OF 2 (4.12) (4-6)<br />
Co-Chairs: Stephane Belbeze, Antea Group (France)<br />
Jeroen Welbergen, COVRA (Netherlands)<br />
Organizer: Didier Dubot<br />
Reviewers: Stephane Belbeze and Jeroen Welbergen<br />
1. Sampling in Decommissioning: CETAMA Seminar and<br />
International Overview (w/oP-59209)<br />
Guy Granier, Daniele Roudil, CEA MARCOULE; Didier Dubot,<br />
CEA/FAR/USLT/SPRE/SAS (France)<br />
2. Foam Novel Delivery Technology for Remediation of Vadose<br />
Zone Environments (wP-59019)<br />
Dawn Wellman, Danielle P Jansik, Shas Mattigod, Lirong<br />
Zhong, Pacific Northwest National Laboratory; Yuxin Wu,<br />
Lawrence Berkeley National Lab; Martin Foote, MSE<br />
Technology Applications; Z. F. (Fred) Zhang, Pacific Northwest<br />
National Laboratory; Susan Hubbard, Lawrence Berkeley<br />
National Lab (USA)<br />
3. Mobility of Radium from Pyritic Uranium Mine Tailings<br />
under Sub-aqueous Disposal Conditions (wP-59283)<br />
Nand Dave, Mining and Mineral Sciences Laboratories Canada<br />
(Canada)<br />
4. Remediation Project Planning at the Uranium Production<br />
Legacy Sites. Lesson Learned from the Best International<br />
Practice and Challenges for Developing Countries<br />
(wP-59043)<br />
Oleg Voitsekhovych, Ukrainian Hydrometeorological Institute<br />
(Ukraine)<br />
5. Close-Out of Open Pit and Waste Rock Piles of Daxin<br />
Uranium Mine of China (wP-59073)<br />
Lechang Xu, Changshun Ren, Min Shi, Liaoning Xueli Zhang,<br />
Jie Gao, Beijing Research Institute of Chemical Engineering<br />
and Metallurgy, CNNC (China)<br />
(MERGED WITH SESSION 34)<br />
SESSION 35<br />
SESSION 36<br />
Wednesday: 10:45am - 12:30pm Room: 10<br />
RADIUM REMEDIATION: HISTORICAL PERSPECTIVES<br />
AND CURRENT CIRCUMSTANCES - PART 1 OF 3 (4.11)<br />
Co-Chairs: Robert Zelmer, Atomic Energy of Canada Limited<br />
(Canada)<br />
Steve Brown, SENES Consultants Ltd. (USA)<br />
Organizers/Reviewers: Robert Zelmer & Steve Brown<br />
1. Radium Diagnosis Campaign (wP-59327)<br />
Florence Gabillaud-Poillion, Autorité de Sûreté Nucléaire<br />
(France)<br />
2. Andra’s Remediation Missions (w/oP-59210)<br />
Patrick Poiret, Eric Lanes, Andra (France)<br />
3. Uranium Mill Tailings Remediation in the USA. A History<br />
and Lessons Learned (w/oP-59407)<br />
Steve Rima, AMEC (USA)<br />
4. Remediation of Canada’s Historic Haul Route for Radium<br />
and Uranium Ores: The Northern Transportation Route<br />
(wP-59303)<br />
Robert Brian Geddes, Chris Wenzel, AMEC; Michael Owen,<br />
Mark J. Gardiner, AECL; Julie Brown, Natural Resources<br />
Canada’s (Canada)<br />
27
Wednesday AM Technical Sessions<br />
SESSION 37<br />
Wednesday: 8:30 - 10:15 Room: 5<br />
YOUNG GENERATION NETWORK (YGN) AND<br />
PROFESSIONAL DEVELOPMENT PROGRAMS (5.16)<br />
Co-Chairs: Corhyn Parr, Nuclear Enterprise Ltd (UK)<br />
Connor Deehan, Nukem (UK)<br />
Organizer/Reviewer: Corhyn Parr<br />
1. The Reestablishment of Radiochemistry Academic <strong>Program</strong>s<br />
in the United States (w/oP-59025)<br />
Craig Williamson, South Carolina Universities Research and<br />
Education Foundation (USA)<br />
2. Planning for Decommissioning of Nuclear Facilities - the<br />
Views of Younger Stakeholders (wP-59222)<br />
Staffan Lindskog, Swedísh Radiation Safety Authority; Bea<br />
Labor, Badania Dydaktycne Project 2010 (Sweden/Poland)<br />
(<strong>Final</strong> paper received and Copyrights pending)<br />
3. Graduate or Apprentice? How Nuclear Training Provision<br />
has Changed the Shape of the Nuclear Employment Market<br />
(w/oP- 59415)<br />
Corhyn Parr, Nuclear Enterprise (UK)<br />
4. Nuclear Knowledge Development - Overview of the<br />
Activities Proposed by SFEN Young Generation (SFEN-JG)<br />
Guillaume Vaast, SGN–Pierrelatte (France)<br />
SESSION 38<br />
Wednesday: 10:45am - 12:30pm Room: 5<br />
MEETING: YOUNG GENERATION NETWORK (YGN) AND<br />
PROFESSIONAL DEVELOPMENT PROGRAMS (5.17)<br />
Co-Chairs: Corhyn Parr, Nuclear Enterprise Ltd. (UK)<br />
Connor Deehan, Nukem (UK)<br />
Organizers: Corhyn Parr<br />
A general YGN Meeting will be conducted to canvass views of the<br />
younger members of the industry, exchange knowledge across<br />
companies, and grow the YGN network through the conference<br />
attendees. This meeting will be used to share best practices, and<br />
develop new ideas to progress the aims and objectives of the YGN in<br />
the future. Agenda: 1) Introductions; 2) Explanation of YGN Aims and<br />
Objectives; 3) Discussion on Output of YGN Questionnaire;<br />
4)Sharing of International YGN Activities and <strong>Events</strong>; 5) Personal<br />
Development and Career Progression; 6) Education and Training<br />
Initiatives; 7) Communications across the YGN Network; 8) External<br />
Communications to wider industry and 9) Future Plans and New<br />
Initiatives.<br />
For the session we conduct ‘An audience with…….’ where two<br />
leaders of industry provide candid views of their career paths and offer<br />
advice to young professionals answering any questions and providing<br />
advice on career development.<br />
Presenters Include: Sarah Greenwood, AREVA (UK); and Jim<br />
Blankenhorn, Permafix Environmental Services Inc.<br />
SESSION 39A<br />
Wednesday: 8:30am - 5:45pm Room: Exhibit Hall<br />
POSTER SESSION: FACILITY DECONTAMINATION AND<br />
DECOMMISSIONING<br />
Co-Chairs: Keith Anderson, ECC (USA)<br />
Didier Delmont, CEA (France)<br />
Reviewers: Keith Anderson and Didier Delmont<br />
A-1. Use of Highly Presurized Liquid Nitrogen Technology for<br />
Concrete Scabbling Application at SICN Nuclear Facilitiy<br />
(wP-59282)<br />
Fabrice Moggia, Claire-Emilie Vaudey, Thierry Varet, Valérie<br />
Toulemonde, AREVA; Frédéric Richard, Air Liquide CTAS;<br />
Gary Anderson, Nitrocision; Frédérique Damerval, AREVA<br />
(France/USA)<br />
28<br />
A-2. Methodology of External Exposure Calculation for Reuse<br />
of Conditional Released Materials from Decommissioning<br />
(wP-59138)<br />
Frantisek Ondra, Marek Vaako, DECOM, a.s.; Vladimir<br />
Necas, Slovak University of Technology (Slovakia)<br />
A-3. Uncertainty Analysis of Activity Measurement of New<br />
Monitoring System for Free-Release for NPP A-1<br />
Decommissioning, Slovakia (wP-59244)<br />
Alojz Slaninka, VUJE, a.s./ Slovak University of Technology<br />
in Bratislava; Ondrej Slávik, VUJE, a.s.; Vladimir Necas,<br />
Slovak University of Technology (Slovakia)<br />
A-4. Laser Removal of Contaminants on the Metal Surface (wP-<br />
59343)<br />
Hui Jun Won, Jei Kwon Moon, Sun Hee Jung, Chong Hun<br />
Jung, Kune Woo Lee, Korea Atomic Energy Research Institute;<br />
Byung -Sun Choi, Korea Atomic Energy Research Institute<br />
(Korea)<br />
A-5. Influence of the Conditional Release of the Materials with<br />
Very Low Level of Radioactivity on the Environment<br />
(wP -59132)<br />
Slavka Prvakova, University of Economics in Bratislava;<br />
Adela Mrskova, DECOM, A. S.; Jozef Pritrsky, DECOM<br />
(Slovakia)<br />
A-6. Conditional Release of Steel from Decommissioning in a<br />
Form of Reinforced Concrete (wP -59058)<br />
Jozef Pritrsky, DECOM; Miroslav Brodnan, University of<br />
Zilina; Vladimir Necas, Slovak University of Technology<br />
(Slovakia)<br />
A-7. Decommissioning of the UF6 Sphere (w/oP -59200)<br />
Sylvain Chevassu, ONET Technologies - ONECTRA (France)<br />
A-8. Development of Nuclear Facilities Piping Cleaning System<br />
using Microbubble (w/oP-59070)<br />
Jongseon Jeon, SangChul Lee, Byoungsub Han, Enesys Co.,<br />
LTD.; HakSoo Kim, Nuclear Engineering & Technology<br />
Institute; Wisoo Kim, Enesys Co., Ltd. (Korea)<br />
A-9. A Matrix Inversion Method For Gamma-Source Mapping<br />
From Gamma Count Data (wP -59082)<br />
Richard Bull, Claire Burgess, Ian Adsley, Nuvia Limited (UK)<br />
A-10. Decommissioning Activities for Salaspils Research Reactor<br />
(wP -59055)<br />
Andris Abramenkovs, Latvian Environment, Geology and<br />
Meteorology Centre; Jazeps Malnacs, State Environmental<br />
Service (Latvia)<br />
A-11. Technical Justification & Choice for Remediation Methods<br />
(wP -59398)<br />
Mark Morton, Janaka Jayamaha, WorleyParsons (USA)<br />
A-12. New Generation of Diamond Toolings for Facilitating<br />
Decommissioning Operations (wP-59396)<br />
Claude Besson, Erico Mariotti, Alexandre Mouysset, Lorenz<br />
Zur Nedden, Bernard Delannay, Carbodiam (France/Belgium)<br />
A-13. Pompe Secondaire (w/oP -59413)<br />
Anne Durand, CEA (France)<br />
A-14. Tritium Analysis : An Actual Problem for Large Building<br />
Decommissioning (w/oP-59406)<br />
Pascal Fichet, Florence Goutelard, Sylvie Guegan, Aurelie<br />
Robert-Ortis, Nadine Evenat-Robic, Commissariat à l’Energie<br />
Atomique (France)<br />
A-15. Reuse of Conditionally Released Steels; Proposal and<br />
Evaluation of Processes for Manufacturing of Steel<br />
Elements and for Construction of Selected Scenarios (wP-<br />
59130)<br />
Peter Bezák, Eva Hajková, Frantisek Ondra, Vladimír<br />
Daniska, DECOM, a.s.; Vladimir Necas, Slovak University of<br />
Technology (Slovakia)<br />
A-16. The Assessment of the Waste Management Plan to<br />
Decommissioning of Cernavoda NPP for Environmental<br />
Impact Reduction (wP -59358)<br />
Gheorghe Barariu, National Authority for Nuclear Activity -<br />
Subsidiary of Technology and Engineering for Nuclear Project<br />
(Romania)<br />
A-17. Application of the Data Quality Objective Process to the<br />
Partial De-Licensing at Oldbury Nuclear Power Station<br />
(wP -59376)<br />
Denis Buckley, Magnox Ltd, Berkeley (UK)
Technical Sessions Wednesday AM<br />
A-18. Multi-Site Risk-Based Project Planning, Optimization,<br />
Sequencing & Budgeting Process and Tool for the<br />
Integrated Facility Disposition Project (wP -59394)<br />
Jerel Nelson, Carlos Castillo, Julie Huntsman, Heather Lucek,<br />
WorleyParsons; Tim Marks, Omega Consultants (USA)<br />
SESSION 39B<br />
Wednesday: 8:30am - 5:45pm Room: Exhibit Hall<br />
POSTER SESSION: ENVIRONMENTAL REMEDIATION<br />
POSTERS (4.1)<br />
Co-Chairs: Lucien Pillette-Cousin, Areva TA (France)<br />
Michel Dutzer, Andra (France)<br />
Reviewers: Lucien Pillette-Cousin and Michel Dutzer<br />
B-1. Radium Remediation in Canada - History and Present Day<br />
(w/oP-59157)<br />
Mark Gardiner, Michael Owen, Robert Zelmer, AECL<br />
(Canada)<br />
B-2. Mathematical Modeling of Reactive Transport in<br />
Groundwater with Metals and Dissolved Isotopes 226Ra<br />
and 228Ra, USIN, São Paulo, Brazil (w/oP-59245)<br />
Rodrigo Raposo de Almeida, Federal Fluminense University;<br />
Valter Mortágua, Industrias Nucleares do Brasil; Felipe Rosa,<br />
Luciano Magalhaes, Universidade Federal Fluminense<br />
(Brazil)<br />
B-3. Quantifying the Retention of Foam Formulation<br />
Components to Sedimentary Phases to Enable Predictions<br />
of Mobility and Treatment Efficacy (w/oP-59369)<br />
Rosa Ramirez, DOE EM; Danielle Jansik, Dawn Wellman,<br />
Pacific Northwest National Laboratory (USA)<br />
B-4. Techniques of Radioactive Soil Processing at Rehabilitation<br />
of Contamination Territories. (wP-59199)<br />
Victor Volkov, Alexander Chesnokov, Alexey Danilovich, Yury<br />
Zverkov, Sergey Koltyshev, Sergey Semenov, Anatoly Shisha,<br />
RRC Kurchatov Institute (Russia)<br />
B-5. Optimisation (Sampling Strategies and Analytical<br />
Procedures) for Site Specific Environment Monitoring at<br />
the Areas of Uranium Legacy Sites Contamination<br />
Concern in Ukraine (wP-59045)<br />
Oleg Voitsekhovych, Tatiyana Lavrova, Alexander Kostezh,<br />
Ukrainian Hydrometeorological Institute (Ukraine)<br />
SESSION 39C<br />
Wednesday: 8:30am - 5:45pm Room: Exhibit Hall<br />
POSTER SESSION: MAJOR INSTITUTIONAL ISSUES IN<br />
ENVIRONMENTAL MANAGEMENT / PUBLIC<br />
INVOLVEMENT (5.1)<br />
Co-Chairs: Judith Connell, Fluor Government Group (USA)<br />
Gerald Ouzounian, Andra (France)<br />
Reviewers: Judith Connell and Gerald Ouzounian<br />
C-1. Virtual Reality Technology for Radiation Visualisation<br />
during the Remediation at Andreeva Bay in Russia as<br />
Support to Operational and Regulatory Supervision<br />
(wP-59400)<br />
Niels-Kristian Mark, Institute for Energy Technology,<br />
Malgorzata Sneve, Norwegian Radiation Protection Authority<br />
(Norway)<br />
C-2. Taking Risk Asessment and Management to the Next Level<br />
(wP-59395)<br />
Jerel Nelson, Russel Lee Morton, WorleyParsons Polestar;<br />
Carlos Castillo, WorleyParsons; James T. McSwain,<br />
Terragraphics; George Dyer, Natalie Johnson, WorleyParsons;<br />
Gary Nick Kruskall, Link Technologies (USA)<br />
C-3. Radioactive Waste, from Myth to Reality: The Stakes for<br />
Andra’s Educational Communication Efforts (w/oP-59287)<br />
Annabelle Comte, Andra (France)<br />
SESSION 40<br />
Wednesday: 1:45pm - 6:00pm Room: 2<br />
D&D MANAGEMENT APPROACHES AND PLANNING<br />
TOOLS (3.6)<br />
Co-Chairs: Thierry Varet, AREVA (France)<br />
Sean Bushart, EPRI (USA)<br />
Organizers: Jas S. Devgun and Jean-Guy Nokhamzon<br />
Reviewer: Thierry Varet<br />
1. Implementation of the Standardised Listing into<br />
Decommissioning Costing; Examples and Related IAEA<br />
Projects (wP-59313)<br />
Vladimír Daniska, DECOM, a.s.; Michele Laraia, Paul Dinner,<br />
Patrick O’Sullivan, IAEA (Slovikia/Austria)<br />
2. Use of Source Term and Air Dispersion Modeling in<br />
Planning Demolition of Highly Alpha-Contaminated<br />
Buildings (wP-59254)<br />
James G Droppo, Bruce A. Napier, Jeremy P. Rishel, Pacific<br />
Northwest National Laboratory; Richard W. Bloom, CH2M Hill<br />
Plateau Remediation Company (USA)<br />
3. How and Integrated Change <strong>Program</strong>me has Accelerated<br />
the Reduction in High Risk and High Hazard Nuclear<br />
Facilities at Sellafield (wP-59014)<br />
Angela Mackintosh, Sellafield Ltd. (UK)<br />
4. Use of In-Situ Gamma Spectroscopy During Nuclear Power<br />
Plant Decommissioning (w/oP-59340)<br />
Richard McGrath, Karen Kim, Electric Power Research Institute<br />
(USA) - Presentation by Sean Bushart, EPRI (USA)<br />
— BREAK —<br />
5. Legacy Radioactive Waste Storage - Magnox Swarf Storage<br />
Silo Liquor Effluent Management (wP-59271)<br />
Stephen Le Clere, Sellafield Ltd (UK)<br />
6. Experience of Application of New Remote Controlled<br />
Instruments for Scanning of Distribution of Radioactive<br />
Contamination in Rooms with High Dose Rate (wP-59354)<br />
Vyacheslav Stepanov, Alexey Danilovich, Oleg Ivanov, Victor<br />
Potapov, Sergey Smirnov, Anatoly Volkovich, NRC Kurchatov<br />
Institute (Russia)<br />
7. Human and Organisational Factors as Key Levers of<br />
Performance in D&D Project Management (w/oP-59323)<br />
Thierry Flament, Bertrand Willmann, Grégoire de Laval, Jean-<br />
Louis Lemarch, Alain Cordoba, AREVA (France)<br />
8. Development of Computer <strong>Program</strong> for Estimating<br />
Decommissioning Cost (wP-59037)<br />
HakSoo Kim, JongKil Park, Nuclear Engineering & Technology<br />
Institute (Korea)<br />
SESSION 41<br />
Wednesday: 1:45pm - 6:00pm Room: 3<br />
D&D TECHNOLOGIES - PART 2 OF 2 (3.13)<br />
Co-Chairs: Jas S. Devgun, Sargent & Lundy (USA)<br />
Bernard Vignau, CEA (France)<br />
Organizer: Jas Devgun<br />
Reviewers: Jas Devgun and Bernard Vignau<br />
1. An Innovative Process for Segmenting of Guide Tubes (wP-<br />
59029)<br />
Patrick (PJ) Gobert, Pierre-Henri Ponchon, Stefan Fallström,<br />
Joseph Boucau, Westinghouse Electric Company<br />
(Belgium/France/Sweden)<br />
2. Assay of Plutonium Contaminated Waste by Gamma<br />
Spectrometry (wP-59039)<br />
Ian Adsley, Michael Green, Ian Pearman, Mike Davies, Nuvia<br />
Limited (UK)<br />
3. Reuse of Conditional Released Materials from<br />
Decommissioning; A Review of Approaches and Scenarios<br />
with Long-Term Constructions (w/oP-59149)<br />
Vladimír Daniska, Jozef Pritrsky, Frantisek Ondra, Ivan Rehák,<br />
Matej Zachar, DECOM, a.s,; Vladimir Necas, Slovak University<br />
of Technology (Slovakia)<br />
29
Wednesday PM Technical Sessions<br />
4. Remediation of a Ventilation Duct Contaminated by Pa-231<br />
(wP-59248)<br />
Pete Burgess, Nuvia Ltd; Clare Irving, Forest Environmental;<br />
Keith Stevens, Nuvia Ltd, (UK)<br />
— BREAK —<br />
5. Measurement of Plutonium Contamination through Paint<br />
Using a Fidler Probe (wP-59250)<br />
Robert Clark, Pete Burgess, Nuvia Ltd; Ian Croudace, GAU-<br />
Radioanalytical Laboratories (UK)<br />
6. The Use of Standard Alpha and Beta Surface Scintillation<br />
Contamination Monitors to Confirm the Contamination<br />
Fingerprint and to Check on Source Quality (wP-59249)<br />
Pete Burgess, Nuvia Ltd (UK)<br />
7. Clearance of Buildings of NPP Würgassen (Germany) Using<br />
an Innovative Clearance Concept (wP-59280)<br />
Stefan Woerlen, Marco Steinbusch, Alexander Kummer, Stefan<br />
Thierfeldt, Frank Schartmann, Brenk Systemplanung (Germany)<br />
8. Characterization of Iraq’s Remote Nuclear Facilities for<br />
Decommissioning and Waste Management (wP-59167)<br />
Fouad Al-Musawi, Adnan S. Jarjies, Ministry of Science and<br />
Technlogy; Ross Miller, Sandia National Laboratories<br />
(Iraq/USA)<br />
SESSION 42<br />
Wednesday: 1:45pm - 6:00pm Room: 5<br />
LIQUID WASTE TREATMENT PROCESS AND EXPERIENCE<br />
(1.8)<br />
Co-Chairs: Michael Ojovan, University of Sheffield (UK)<br />
Andrew Drom, EnergySolutions EU Ltd. (UK)<br />
Organizers/Reviewers: Michael Ojovan and Paul Haigh<br />
1. Nuclide Separation by Hydrothermal Treatment and Ion<br />
Exchange (wP-59217)<br />
Georg Braehler, Ronald Rieck, NUKEM Technologies GmbH;<br />
Valentin Avramenko, Valentin Sergienko, Sergej Shmatko,<br />
Valentin Dobrzhanskyi, Institute of Chemistry FEBRAS; Elmar<br />
Antonov, NTP (Germany/Russia)<br />
2. Decontamination of Strontium from Liquid Radioactive<br />
Wastes by Sodium Nonatitanate (wP-59083)<br />
Merceille Aurélie, CEA Marcoule; Agnès Grandjean, Institut de<br />
Chimie Séparative de Marcoule; Yves Barre, CEA Marcoule<br />
(France)<br />
3. Russia: Results and Prospects of Liquid Solidification<br />
Experiments at ROSATOM Sites (w/oP-59112)<br />
Dennis Kelley, Pacific Nuclear Solutions (USA)<br />
4. Pre-Treatment of Organic Liquid Waste Stream at<br />
Cernavoda NPP (w/oP-59079)<br />
Gabriela Teodorov, Laszlo Toro, Adina Sandru, MATEFIN;<br />
Dennis Kelley, Pacific Nuclear Solutions; Dorin Dumitrescu,<br />
NPP Cernavoda (Romania/ USA)<br />
— BREAK —<br />
5. Transport and Deposition Properties of Model Slurries of<br />
One and Two Particle Species (wP-59140)<br />
Hugh Rice, Simon Biggs, Michael Fairweather, James Young,<br />
University of Leeds, Leeds, (UK)<br />
6. Application of a New Technology For Reprocessing of<br />
Wastes Within the Framework of Rehabilitation of Uranium<br />
Mines Operated by In Situ Leaching (wP-59403)<br />
Gagik Martoyan, Garik Nalbandyan, Lavrenti Gagiyan,<br />
AREV SI CJS Company; Gagik Karamyan, Artak Barseghyan,<br />
Gagik Brutyan, Ecoatom LLC (Armenia)<br />
7. A Fully Operational Pilot Plant for Eliminating Radioactive<br />
Oils Mixed with Chlorinated Solvents (wP-59044)<br />
Albert Jacobs, William Everett, Dewdrops Company (France)<br />
8. Adsorption of Cesium Radionuclides by the Composite<br />
Sorbents Carbon Fiber/Transition Metals Ferrocyanides<br />
(wP-59255)<br />
Irina Sheveleva, Veniamin Zheleznov, Svetlana Bratskaya,<br />
Valeriy Kuryavyi, Valentin Avramenko, Institute of Chemistry<br />
FEBRAS (Russia)<br />
30<br />
SESSION 43<br />
Wednesday: 1:45pm - 3:30pm Room: 6<br />
SITING, DESIGN, CONSTRUCTION, AND OPERATION OF<br />
L/ILW DISPOSAL FACILITIES - PART 2 OF 2 (1.19)<br />
Co-Chairs: Cathy Hickey, CH2M Hill (USA)<br />
Patrice Torres, Andra (France)<br />
Organizers/Reviewers: Cathy Hickey and Philip Rendell<br />
1. 20 Years of Operation for Centre de l’Aube Disposal<br />
Facility: Lessons Learned (w/oP-59235)<br />
Patrice Torres, Laurent Schacherer, Franck Duret, Pascal<br />
Lecoq, Alain Delaplanche, Michel Dutzer, Andra (France)<br />
2. Demonstration Test of Underground Cavern-Type Disposal<br />
Facilities Fiscal 2010 Status (w/oP-59180)<br />
Yoshihiro Akiyama, Kenji Terada, Nobuaki Oda, Tsutomu Yada,<br />
Takahiro Nakajima, Radioactive Waste Management Funding<br />
And Research Center (Japan)<br />
3. Demonstration of Gas Permeable Seals for Radioactive<br />
Waste Repositories Laboratory and In-Situ Experiments<br />
(wP-59224)<br />
Joerg Rueedi, Paul Marschall, Nagra (Switzerland)<br />
4. Post-Iodine Production Norm Repository Technical Design<br />
and Reconstruction Experience in Turkmenistan<br />
(wP-59183)<br />
Alexander Gelbutovsky, Peter Cheremisin, Alexander Troshev,<br />
Alexander Egorov, Mikhail M. Boriskin, Mikhail Bogod,<br />
ECOMET-S (Russia)<br />
SESSION 44<br />
Wednesday: 4:15pm - 6:00pm Room: 6<br />
DISPOSAL SITE AND WASTE FORM CHARACTERIZATION<br />
AND PERFORMANCE ASSESSMENT - PART 1 OF 2 (1.13)<br />
Co-Chairs: Ed Bentz, E.J. Bentz & Associates (USA)<br />
Michel Dutzer, Andra (France)<br />
Organizer: Donald Goebel<br />
Reviewers: Ed Bentz and Michel Dutzer<br />
1. Radiological Characterization of the Dutch Interim Waste<br />
Storage Facility Site (w/oP-59023)<br />
Jeroen Welbergen, COVRA; Leo P.M. Velzen, Nuclear Research<br />
and Consultancy Group (Netherlands)<br />
2. Climate Change Impacts on the Disposal Environment: A<br />
Climate Analogue Approach (wP-59274)<br />
Bertrand Leterme, Dirk Mallants, SCK●CEN (Belgium)<br />
3. Mineralogical Analyses of Old (78 and 98 years) Concrete<br />
(wP-59093)<br />
Tomoko Ishii, Hitoshi Owada, Radioactive Waste Management<br />
Funding and Research Center; Hiroyuki Sakamoto, Masahito<br />
Shibata, Kumi Negishi, Taiheyo Consultant Co.,Ltd. (Japan)<br />
4. Modeling of Alteration Behavior on Blended Cementitious<br />
Materials (wP-59096)<br />
Hitoshi Owada, Tomoko ISHII, Radioactive Waste Management<br />
Funding and Research Center; Mayumi Takazawa, Hiroyasu<br />
Kato, Mitsubishi Materials Corporation; Hiroyuki Sakamoto,<br />
Taiheyo Consultant Co.,Ltd.; Masahito Shibata, Taiheyo<br />
Consultant Co., Ltd. (Japan)
Technical Sessions Wednesday PM<br />
SESSION 45<br />
Wednesday: 1:45pm - 3:30pm Room: 10<br />
REPOSITORY PROGRAMS: SITE SELECTION &<br />
CHARACTERIZATION, UNDERGROUND RESEARCH LABS,<br />
ENGINEERING & GEOLOGICAL BARRIERS - PART 2 OF 2<br />
(2.7)<br />
Co-Chairs: Bill Miller, AMEC (UK)<br />
Johan Andersson, JA Streamflow AB (Sweden)<br />
Organizers/Reviewers: Bill Miller and Johan Andersson<br />
1. EBS Behavior Immediately After Repository Closure in a<br />
Clay Host Rock: The HE-E Experiment (Mont Terri URL)<br />
(wP-59288)<br />
Irina Gaus, Nagra; Klaus Wieczorek, GRS; Juan Carlos Mayor,<br />
ENRESA; Kristof Schuster, BGR; Thomas Trick, Solexperts;<br />
José-Luis Garcia-Siñeriz, Aitemin; Benoit Garitte, CIMNE; Uli<br />
Kuhlman, TK Consult (Switzerland/Germany/Spain)<br />
2. Performance Assessment Modeling for the Geological Siting<br />
Regions for the L/ILW and HLW Repositories in the Context<br />
of the Swiss Site Selection Plan (wP-59306)<br />
Andreas Poller, Juerg Schneider, Piet Zuidema, Nagra;<br />
Johannes Holocher, Gerhard Mayer, AF-Consult Switzerland<br />
Ltd. (Switzerland)<br />
3. Investigations of the Possible Separation Distance between<br />
Spent Fuel/High-Level Waste and a Low/Intermediate-Level<br />
Waste Repositories Due to Gas and Heat Generation<br />
(wP-59220)<br />
Rainer Senger, John Ewing, Intera Inc. Swiss Branch;<br />
(Switzerland)<br />
4. Hydraulic/Mechanical Modeling of Smectitic Materials for<br />
HMC Analytical Evaluation of the Long Term Performance<br />
of TRU Geological Repository (wP-59090)<br />
Ichizo Kobayashi, Kajima Corporation; Hitoshi Owada,<br />
Tomoko Ishill, Radioactive Waste Management Funding and<br />
Research Center (Japan)<br />
SESSION 46<br />
Wednesday: 4:15pm-6:00pm Room: 10<br />
NATIONAL AND INTERNATIONAL PROGRAMS FOR SPENT<br />
FUEL, FISSILE, TRU, AND HLW MANAGEMENT (2.2)<br />
Co-Chairs: Paul Dixon, LANL (USA)<br />
Bernard Vigreux, SFEN (France)<br />
Organizer: Hans Codee<br />
Reviewers: Bernard Vigreux and Hans Codee<br />
1. Implications of Co-existing National and Multinational<br />
Geological Repository Development <strong>Program</strong>mes in Europe<br />
(wP-59118)<br />
Neil A. Chapman, Charles McCombie, Arius Association;<br />
Ewoud Verhoef, Covra (Switzerland/Netherlands)<br />
2. Regulation of Ageing Facilities - The UK Regulators<br />
Perspective (wP-59353)<br />
Ryan Maitland, Unit 2G Nuclear Installations Inspectorate<br />
(UK)<br />
3. Establishment of Research and Development Priorities<br />
Regarding the Geologic Disposal of Nuclear Waste in the<br />
United States and Strategies for International Collaboration<br />
(wP-59168)<br />
Mark Nutt, Argonne National Laboratory; Michael Voegele,<br />
Complex Systems LLC; Jens Birkholzer, Lawrence Berkeley<br />
National Laboratory; Peter Swift, Sandia National<br />
Laboratories; Jeff Williams, U.S. Department of Energy; Kevin<br />
McMahon, Sandia National Laboratories; Mark Peters,<br />
Argonne National Laboratory (USA)<br />
4. The Cigéo Geological Repository Project (wP-59265)<br />
Thibaud Labalette, Alain Harman, Marie-Claude Dupuis,<br />
Andra (France)<br />
SESSION 47<br />
Wednesday: 1:45pm - 3:30pm Room: 1<br />
RADIUM REMEDIATION HISTORICAL PERSPECTIVES<br />
AND CURRENT CIRCUMSTANCES - PART 2 OF 3 (4.47)<br />
Co-Chairs: Robert Zelmer, Atomic Energy of Canada Limited<br />
(Canada)<br />
Gerald Ouzounian, Andra (France)<br />
Organizers/Reviewers: Robert Zelmer and Gerald Ouzounian<br />
1. Port Radium Start to Finish Life Cycle: A Case Study on<br />
Canada’s Historic Radium/Uranium Mine, Initial Operation<br />
and Closure, Concerns of the Aboriginal Dene People,<br />
Subsequent Assessments, Remediation (wP-59332)<br />
Gerd Wiatzka, SENES Consultants Ltd. (Canada)<br />
Presentation by Steve Brown, SENES Consultants Ltd (USA)<br />
2. Challenges in Developing a Remediation Plan, Procurement<br />
Plan and Long Term Monitoring <strong>Program</strong> for the Former<br />
Port Radium Uranium Mine that Meets the Needs of the<br />
Community of Deline (w/oP-59333)<br />
Julie Ward, Indian and Northern Affairs Canada (Canada)<br />
3. Overview of Radium Legacies in Belgium (wP-59367)<br />
Stephane Pepin, Koen Mannaerts, Boris Dehandschutter, André<br />
Poffijn, Ludo Jadoul, Walter Blommaert, Michel Sonck, FANC<br />
(Belgium)<br />
4. Preparing for the Construction Phase of The Port Hope Area<br />
Initiative: Canada’s Largest Low-Level Radioactive Waste<br />
Clean-up Project (wP-59307)<br />
Christine Fahey, Andrea Denby, Glenn Case, Atomic Energy of<br />
Canada Ltd.; Tim Palmeter, Public Works Government Services<br />
Canada (Canada)<br />
SESSION 48<br />
Wednesday: 4:15pm - 6:00pm Room: 1<br />
RADIUM REMEDIATION - HISTORICAL PERSPECTIVES<br />
AND CURRENT CIRCUMSTANCES - PART 3 OF 3 (4.13)<br />
Co-Chairs: Robert Zelmer, Atomic Energy of Canada Limited<br />
(Canada)<br />
Gerald Ouzounian, Andra (France)<br />
Organizers: Robert Zelmer and Gerald Ouzounian<br />
An international panel will discuss and compare progress and history<br />
of national radium remediation programs. Lessons learned will be<br />
featured and shared. The outlook for the final closure on this issue<br />
worldwide will also be addressed. The perspectives and panelists<br />
invited include those from practitioners in government policy<br />
leadership, regulatory oversight and licensing, health and safety<br />
impacts and protection, environmental remediation practice and<br />
affected community stakeholders.<br />
Panelists include: Stéphane Pepin, FANC (Belgium); Keith<br />
McConnell, USNRC (USA); Jean-Luc Lachaume, ASN (France); and<br />
Steve Brown, SENES Consultants Ltd. (USA)<br />
SESSION 49<br />
Wednesday: 1:45pm - 3:30pm Room: 4<br />
PANEL: COMMUNICATIONS AND KNOWLEDGE<br />
MANAGEMENT - PART 1 OF 2 (5-21)<br />
Co-Chairs: Jim Marra, US DOE (USA)<br />
Ian Seed, Cogentus Consulting Limited (UK)<br />
Organizer: Jim Marra<br />
This is a two part series of paper presentations and a following panel<br />
session discussion on communications and knowledge management.<br />
Current efforts and views will be presented during this first session.<br />
This session is directly followed by the second part, Panel Session<br />
#50. Presenters will each provide a 10-15 minute overview to the<br />
audience before the break, and will then resume on this topic.<br />
Panelists include: Laurie Judd, NuVision Engineering (USA);<br />
Leonel Lagos, Florida International University (USA); Yanko Yanev,<br />
IAEA (Austria); Hitoshi Makino, JAEA (Japan); Bill Shingler, Fluor<br />
Government Group (USA) and Herve Bienvenu, Andra (France)<br />
31
Wednesday PM Technical Sessions<br />
SESSION 50<br />
Wednesday: 4:15pm - 6:00pm Room: 4<br />
PANEL: COMMUNICATIONS AND KNOWLEDGE<br />
MANAGEMENT - PART 2 OF 2 (5-21)<br />
Co-Chairs: Jim Marra, US DOE (USA)<br />
Ian Seed, Cogentus Consulting Limited (UK)<br />
Organizer: Jim Marra<br />
This panel will provide strategies and lessons learned regarding<br />
general communications and knowledge management to a wide<br />
variety of target audiences, and discuss the earlier presentations.<br />
Communication and management of technical information is a<br />
challenging endeavor. Target groups for technical communications<br />
range from the general public with a cursory knowledge of the subject<br />
matter to highly technical personnel heavily engaged in the work<br />
scope. Communications to the general republic requires deft wording<br />
of technical content and use of attention-grabbing graphics and<br />
illustrations. Managing technical content for highly technical<br />
personnel requires thorough cataloging of subject matter and<br />
providing easy recall and use.<br />
Panelists include: Laurie Judd, NuVision Engineering (USA);<br />
Leonel Lagos, Florida International University (USA); Yanko Yanev,<br />
IAEA (Austria); Hitoshi Makino, JAEA (Japan); Bill Shingler, Fluor<br />
Government Group (USA) and Herve Bienvenu, Andra (France)<br />
SESSION 51<br />
Thursday: 8:30am - 12:30pm Room: 2<br />
SAFETY CONSIDERATIONS ASSOCIATED WITH L/ILW<br />
MANAGEMENT (1.14)<br />
Co-Chairs: Stephen Wickham, Galson Sciences Limited (UK)<br />
Adam Meehan, EnergySolutions/Magnox Ltd. (UK)<br />
Organizers/Reviewers: Stephen Wickham and Ian Crossland<br />
1. UK LLWR Environmental Safety Case Submission 2011<br />
(wP-59135)<br />
Richard Cummings, LLWR Ltd; Andrew Baker, LLWR; Trevor<br />
Sumerling, LLWR; John Shevelan, Amy Huntington, LLWR Ltd.<br />
(UK)<br />
2. An Assessment of the Radiological Impact of Coastal<br />
Erosion of the UK Low-Level Waste Repository (wP-59137)<br />
Trevor Sumerling, LLWR; Paul Fish, Halcrow Ltd.; George<br />
Towler, James Penfold, Quintessa Ltd; John Shevelan, Richard<br />
Cummings, LLWR Ltd. (UK)<br />
3. Development of a Methodology for Determining ILW<br />
Package Monitoring and Inspection Requirements (wP-<br />
59156)<br />
Jenny E. Morris, Timothy W. Hicks, Stephen M. Wickham,<br />
Galson Sciences Limited; Antonio Guida, Babcock International<br />
Group; Melanie Brownridge, James McKinney Darrell Morris,<br />
Nuclear Decommissioning Authority; Mark Tearle, Magnox<br />
Limited (UK)<br />
4. An Assessment of the Radiological Impact of Human<br />
Intrusion at the UK Low Level Waste Repository (LLWR)<br />
(wP-59356)<br />
Timothy Hicks, Tamara Baldwin, Galson Sciences Ltd; Richard<br />
Cummings, LLWR Ltd.; Trevor Sumerling, LLWR (UK)<br />
— BREAK —<br />
5. Factors Affecting the Longevity of Interim ILW Stores,<br />
Monitoring Methods and Techniques Supporting Store Life<br />
Extension (wP-59151)<br />
Jenny E. Morris, Stephen Wickham, Timothy Hicks, Phil J.<br />
Richardson, Galson Sciences Limited; Melanie Brownridge,<br />
Darrell Morris, James McKinney, Nuclear Decommissioning<br />
Authority; Mark Tearle, Magnox Limited (UK)<br />
6. Different Types of Radioactive Waste Repositories, each<br />
Suited for a Given Type of Radioactive Waste (wP-59293)<br />
Sylvie Voinis, Fabrice Boissier, Lise Griffault, Jean Louis<br />
Maillard, Michel Dutzer, Andra (France)<br />
32<br />
SESSION 52<br />
Thursday: 8:30am - 12:30pm Room: 3<br />
DISPOSAL SITE AND WASTE FORM CHARACTERIZATION<br />
AND PERFORMANCE ASSESSMENT - PART 2 OF 2 (1.20)<br />
Co-Chairs: Bill Miller, AMEC (UK)<br />
Patrice Torres, Andra (France)<br />
Organizer/Reviewer: Donald Goebel<br />
1. Characterisation of the Geology of the UK Low Level Waste<br />
Repository (wP-59146)<br />
John Shevelan, LLWR Ltd; Nicholas Smith, National Nuclear<br />
Laboratory (UK)<br />
2. In-Situ Interferometric Measurements of Compacted<br />
Smectite under Hyperalkaline Condition (w/oP-59124)<br />
Hisao Satoh, Susumu Kurosawa, Mitsubishi Materials<br />
Corporation; Tomoko Ishii, Hitoshi Owada, Radioactive Waste<br />
Management Funding and Research Center (Japan)<br />
3. Evolution of Sorption Properties in Large-Scale Concrete<br />
Structures Accounting for Long-Term Physical-Chemical<br />
Concrete Degradation (wP-59297)<br />
Janez Perko, Dirk Mallants, Diederik Jacques, Suresh<br />
Seetharam, SCK●CEN, (Belgium)<br />
— BREAK —<br />
4. Biogeochemical Modelling of the Chemical Evolution of the<br />
Near Field of the UK LLW Repository and effects on<br />
Carbon-14 Release (w/oP-59150)<br />
Joe Small, Christopher Lennon, Liam Abrahamsen, UK<br />
National Nuclear Laboratory; Andrew J. Baker, LLWR (UK)<br />
5. Characterisation and Assessment of the Groundwater<br />
Pathway for the Low Level Waste Repository, UK (wP-<br />
59098)<br />
Lee Hartley, Martin James, Peter Jackson, Matt Couch,<br />
SERCO; John Shevelan, LLWR Ltd (UK)<br />
SESSION 53<br />
Thursday: 8:30am - 10:15am Room: 1<br />
GLOBAL PARTNERSHIPS AND NATIONAL INITIATIVES IN<br />
ENVIRONMENTAL MANAGEMENT - PART 1 OF 2 (5.13)<br />
Co-Chairs: Michael Cull, Teledyne Brown Engineering, Inc.<br />
(USA)<br />
Mark Gerchikov, AMEC NSS (Canada)<br />
Organizers/Reviewers: Michel Cull and Mark Gerchikov<br />
1. Russian Nuclear Submarine Elimination 2001 - 2011 by The<br />
International Community (w/oP-59041)<br />
Michael Washer, Foreign Affairs and International Trade<br />
Canada; Alan Heyes, King’s College (Canada/UK)<br />
2. The Global Partnership: Its Achievements, Missed<br />
Opportunities and Potential to Address Future Threats from<br />
the Spread of CBRN Materials and Expertise (w/oP-59335)<br />
Alan Heyes, Wyn Bowen, Hugh Chalmers, King’s College (UK)<br />
3. The Global Threat Reduction Initiatives Radiological<br />
Security Cooperation with Russia (wP-59361)<br />
Tiffany Blanchard, U.S. Department of Energy/National<br />
Nuclear Security Administration; William Abramson, Lawrence<br />
Livermore National Laboratory; James W. (J.R.) Russell,<br />
National Security Technologies; Catherine Roberts, Pacific<br />
Northwest National Laboratory (USA)<br />
4. Kola Peninsula Radwaste Management in the Framework of<br />
the Italian-Russian Cooperation Agreement for Global<br />
Partnership (wP-59392)<br />
Massimiliano Nobile, SOGIN (Russia)<br />
5. Securing of the Spent Nuclear Fuel Stored on Gremikha Site<br />
- The Former Soviet Submarine Base in North-West of<br />
Russia (w/oP-59371)<br />
Alexandre Gorbatchev, CEA; Lucien Pillette-Cousin, AREVA<br />
TA: Boris Stepennov, NRC KI; Valery Eremenko, SevRAO;<br />
Anatoly Zakharchev, ROSATOM (France/Russia)
Technical Sessions Thursday AM<br />
SESSION 54<br />
Thursday: 10:45am - 12:30pm Room: 1<br />
GLOBAL PARTNERSHIP IN ENVIRONMENTAL<br />
MANAGEMENT - PART 2 OF 2 (5.20)<br />
Co-Chairs: Michael Cull, Teledyne (USA)<br />
Mark Gerchikov, AMEC (Canada)<br />
Organizers/Reviewers: Michael Cull and Mark Gerchikov<br />
1. Environmental and Radiological Remediation Under<br />
Canada’s Global Partnership <strong>Program</strong> 2004-11 (wP - 59185)<br />
Michael J. Washer, Foreign Affairs and International Trade<br />
Canada (Canada)<br />
2. UK Contributions to the Decommissioning of the BN-350<br />
Reactor in Kazakhstan: 2002 – 2011 (wP-59099)<br />
Steven Laws, Department of Energy and Climate Change (UK),<br />
David Wells and Andrew Herrick, Nuvia Limited (UK)<br />
3. Dismantling of Civilian Nuclear Powered Fleet Technical<br />
Support Vessels. Engineering Solutions. (wP-59386)<br />
Konstantin Kulikov, Rinat Nizamutdinov, NIPTB Onega OAO<br />
(Russia)<br />
4. Progress in International Cooperation on Regulatory of<br />
Legacy Management: Experience in Norwegian Cooperation<br />
<strong>Program</strong>mes (wP-59399)<br />
Malgorzata Sneve, Norwegian Radiation Protection Authority<br />
(Norway)<br />
5. Methodological and Practical Bases of Providing<br />
Information Support to Activities on Environmental<br />
Remediation of the Spent Nuclear Fuel and Radioactive<br />
Waste Temporary Storage Facility in Gremikha (wP-59375)<br />
Dmitry Stepennov, Anatoly P. Varnavin, NRC Kurchatov<br />
Institute; Anatoly A. Zakharchev, Rosatom; Lucien Pillette-<br />
Cousin, AREVA TA (Russia/France)<br />
SESSION 55<br />
Thursday: 8:30am - 10:15am Room: 4<br />
SAFETY AND SECURITY RELATED TO ENVIRONMENTAL<br />
AND NUCLEAR MATERIALS MANAGEMENT (5.11)<br />
Co-Chairs: Ken Kok, Consultant (USA)<br />
Bernard Vigreux, SFEN (France)<br />
Organizer: Adrian Mendez-Torres<br />
Reviewers: Adrian Mendez-Torres and Philippe Crochon<br />
1. Remote Radiation And Visual Surveys of the Hot Cell Waste<br />
Vault and Spent Fuel Transfer Route at Kazakhstans BN-<br />
350 Reactor (wP-59101)<br />
David Wells, Nuvia Limited, Dorchester,United Kingdom, Collin<br />
Knight, Idaho National Laboratory; Alexander Klepikov,<br />
Nuclear Technology Safety Center; Igor Yakovlev, CRT&TD<br />
MAEC-Kazatomprom LLP; Evgeniy Tur, National Nuclear<br />
Center of the Republic of Kazakhstan; Andrew Herrick, Nuvia<br />
Limited (USA/Kazakhatan/UK)<br />
2. Human Reliability-Based MC&A Modeling for Evaluating<br />
the Effectiveness of Protecting Nuclear Material (wP-59379)<br />
Felicia A Durán, Gregory D. Wyss, Sandia National<br />
Laboratories (USA)<br />
3. Risk-Based Security Cost-Benefit Analysis: Method and<br />
Example Applications (w/oP-59381)<br />
Gregory Wyss, John Hinton, John Clem, Consuelo Silva, Felicia<br />
A Durán, Sandia National Laboratories (USA)<br />
SESSION 56<br />
Thursday: 10:45am - 12:30pm Room: 4<br />
ADVANCED L/ILW TECHNOLOGIES - PART 2 OF 2 (1.21)<br />
Co-Chairs: Ian Beadle, AMEC (UK)<br />
Dominique Greneche, Consultant (France)<br />
Organizer: Angie Jones<br />
Reviewers: Pierre Van Iseghem and Dominique Greneche<br />
1. Applying Fluid Dynamics Simulations to Improve<br />
Processing and Remediation of Nuclear Waste (wP-59172)<br />
Kelly J Knight, Jon M. Berkoe, Brigette M. Rosendall, L. Joel<br />
Peltier, Chris A Kennedy, Bechtel National (USA)<br />
2. Lifetime Performance of ASME AG-1 Section FK Radial<br />
Flow Filters (wP-59170)<br />
Charles Waggoner, Michael Parsons, Paxton Giffen,<br />
Mississippi State University; Jaime Rickert, Institute for Clean<br />
Energy Technology (USA)<br />
3. Alternative Strategies to Reduce Cost and Waste Volume in<br />
HEPA Filtration using Metallic Filter Media (wP-59348)<br />
Chris Chadwick, Porvair Filtration Group (UK)<br />
4. Advanced Drying System to Meet Radiolysis Criteria of<br />
Metallic Waste (wP-59116)<br />
Masamichi Obata, Yasushi Ooishi, Toshiba Corporation<br />
(Japan)<br />
SESSION 57<br />
Thursday: 8:30am - 12:30pm Room: 5<br />
RECENT ADVANCES IN PROCESSING AND<br />
IMMOBILIZATION OF HLW, FISSILE AND TRU -<br />
PART 2 OF 2 (2.6)<br />
Co-Chairs: James Blankenhorn, Permafix Environmental<br />
Services Inc. (USA)<br />
Gerald Ouzounian, Andra (France)<br />
Organizers: Mark Denton and Bill Wilmarth<br />
Reviewers: James Blankenhorn and Gerald Ouzounian<br />
1. Mitigation of Sliding Motion of a Cask-Canister by Fluidstructure<br />
Interaction in an Annular Region (wP-59208)<br />
Tomohiro Ito, Atsuhiko Shintani, Chihiro Nakagawa, Osaka<br />
Prefecture University; Kazuhisa Furuta, Osaka Prefcture<br />
University (Japan)<br />
2. Iodine Conditioning as Iodate Ion in an Apatite-Like<br />
Ceramic (w/oP-59015)<br />
Lionel Campayo, CEA; Danielle Laurencin, Institut Charles<br />
Gerhardt De Montpellier; Agnès Grandjean, Institut De Chimie<br />
Séparative De Marcoule; Remy Delorme, CEA (France)<br />
3. Status of the Development of In-Tank/At-Tank Separations<br />
Technologies for High-Level Waste Processing for the U.S.<br />
Department of Energy (wP-59109)<br />
Bill Wilmarth, SRNL; Nicholas P. Machara, US DOE Office of<br />
Technology Innovation and Deployment; Steve P. Schneider, US<br />
DOE Office of Waste Processing; Reid A. Peterson, PNNL;<br />
Sheryl R. Bush, SRNL (USA)<br />
Presentation by Jim Marra, US DOE (USA)<br />
4. The Development, Testing and Demonstration of a New<br />
Class of Inorganic Ion Specific Media Emphasizing the<br />
Optimization, Stabilization and Volume Reduction of the<br />
<strong>Final</strong> Nuclear Waste Form (w/oP-59126)<br />
Mark Denton, Kurion Inc.; William D. Bostick, MCL, Inc.<br />
(USA)<br />
— BREAK —<br />
5. High Waste Loading Glass Formulations for Hanford High-<br />
Aluminum HLW Streams (wP-59388)<br />
Albert Kruger, US DOE (USA)<br />
6. The Design, Development and Demonstration of a New<br />
Modular Vitrification System (MVS®) for the Treatment of<br />
Nuclear Waste (w/oP-59127)<br />
Mark Denton, Gaetan Bonhomme, Kurion Inc. (USA)<br />
33
Thursday AM Technical Sessions<br />
SESSION 58<br />
Thursday: 8:30am - 12:30pm Room: 10<br />
D&D RADIOLOGICAL CHARACTERIZATION AND<br />
MONITORING (3.5)<br />
Co-Chairs: Maria Lindberg, Studsvik Nuclear AB (Sweden)<br />
Jean-Guy Nokhamzon, CEA/DEN/DADN<br />
(France)<br />
Organizers/Reviewers: Jas S. Devgun and Jean-Guy Nokhamzon<br />
1. Quantifying Tc-99 Contamination in a Fuel Fabrication<br />
Plant (wP-59024)<br />
Pete Burgess, Nuvia Ltd; Carol Darbyshire, Springfield Fuels<br />
Ltd (UK)<br />
2. The Science, Assaying and Waste Sentencing of Activated<br />
Bioshields (wP-59038)<br />
Ian Adsley, Nuvia Limited (UK)<br />
3. Gamma-Ray Imaging for Generating 3D Dose Rate Maps<br />
(wP-59123)<br />
Karl Hughes, Edmund Cracknell, Babcock International Group<br />
(UK)<br />
4. Sampling vs. Taking Some (wP-59349)<br />
Dominique Francois-Bongarcon, AGORATEK International<br />
Consultants (Canada)<br />
— BREAK —<br />
5. Waste Assessment: A Practical Approach to Proving Waste<br />
Metals Suitable for Consignment as Radiologically Exempt<br />
Materials (wP-59266)<br />
Iain Carvel, RSRL; Richard D Gunn, Robin Strange,<br />
Christopher Orr, Babcock International Group (UK)<br />
6. Development of a Computer System for Support and<br />
Documentation of Clearance of Buildings of Nuclear<br />
Installations (wP-59278)<br />
Christoph Winkler, Stefan Woerlen, Stefan Thierfeldt, Frank<br />
Schartmann, Brenk Systemplanung (Germany)<br />
7. Geostatistical Methodology for Waste Optimization of<br />
Contaminated Premises (wP-59344)<br />
Yvon Desnoyers, GEOVARIANCES; Didier Dubot,<br />
CEA/FAR/USLT/SPRE/SAS (France)<br />
8. Discrimination Monitors for Various Kinds of Waste to be<br />
Down Graded (wP-59117)<br />
Susumu Naito, Syuji Yamamoto, Mikio Izumi, Masamichi<br />
Obata, Yukio Yoshimura, Jiro Sakurai, Hitoshi Sakai, Toshiba<br />
Corporation (Japan)<br />
SESSION 59<br />
Thursday: 8:30am - 12:30pm Room: 6<br />
RISK/PERFORMANCE ASSESSMENTS AND CONTAMINANT<br />
MIGRATION (4.7)<br />
Co-Chairs: Michel Dutzer, Andra (France)<br />
Didier Dubot, CEA/FAR/USLT/SPRE/SAS<br />
(France)<br />
Organizers: Steve Brown and Didier Dubot<br />
Reviewers: Gerd Wiatzka and Didier Dubot<br />
1. Uncertainties on the Extension of a Polluted Zone (wP-<br />
59198)<br />
Chantal de Fouquet, Mines ParisTech - Ecole des mines de<br />
Paris (France)<br />
2. Identification and Implementation of End-User Needs<br />
During Development of a State-of-the-Art Modeling Toolset<br />
(wP-59069)<br />
Roger Seitz, SRNL; Mark Freshley, PNNL; Susan Hubbard,<br />
Lawrence Berkeley National Lab; Mark Williamson, US DOE;<br />
Paul Dixon, LANL; Kurt Gerdes, DOE EM; Yvette Collazo , US<br />
DOE (USA)<br />
3. Uranium Investigation in an Alluvial Aquifer with Direct<br />
Push Methods (w/oP-59281)<br />
Fabian De Weirdt, Geoprobe Environmental Technologies s.a.<br />
(Belgium)<br />
34<br />
4. Independent Technical Reviews for Groundwater and Soil<br />
Remediation Projects at US Department of Energy Sites<br />
(w/oP-59188)<br />
Dawn Kaback, AMEC; Grover Chamberlain, DOE EM; John G.<br />
Morse, US DOE; Scott W. Petersen, CH2M Hill (USA)<br />
— BREAK —<br />
5. Advanced Simulation Capability for Environmental<br />
Management (ASCEM) (wP-59065)<br />
Paul Dixon, LANL; Mark Williamson, US DOE; Mark Freshley,<br />
Pacific Northwest National Lab; David Moulton, LANL; Ian<br />
Gorton, Pacific Northwest National Laboratory; Elizabeth H.<br />
Keating, LANL; Yvette Collazo , US DOE; Kurt Gerdes, DOE<br />
EM; Juan Meza, Lawrence Berkeley National Laboratory (USA)<br />
6. A Physiochemical Analysis of the Mechanisms for Transport<br />
and Retention of Technetium (Tc-99) in Unsaturated Soils<br />
(w/oP-59050)<br />
Danielle P Jansik, Dawn Wellman, Elsa Cordova, DeNomy<br />
Dage, PNNL; Dorthe Wildenschild, Oregon State University<br />
(USA)<br />
7. Intermediate and Long-Term Radiological Consequences of<br />
Uncontrolled Saline Solution Access into Asse Mine<br />
(wP-59163)<br />
Veronika Ustohalova, Christian Küppers, Öko-Institut e.V.<br />
(Germany)<br />
8. Cost Benefit Assessment According to French Methodology<br />
(w/oP-59310)<br />
Philippe Pouget-Abadie, Pricop-Bass Tudor, URS (France)<br />
SESSION 60<br />
Thursday: 8:30 - 11:00pm Room: Exhibit Hall<br />
BEST POSTERS OF ICEM 2011<br />
Co-Chairs: Gary Benda, Bartlett Services (USA)<br />
Dominique Greneche, Consultant (France)<br />
Organizer: Gary Benda<br />
This poster session highlights the top posters selected from each of the<br />
five Tracks of ICEM 2011.
Notes<br />
35
36<br />
Notes
Notes<br />
37
38<br />
Exhibition Hours and Exhibitor Floorplan<br />
Exhibitors Listings in Alphabetical Order<br />
BOOTH COMPANY<br />
217 ANDRA<br />
ASME<br />
320 ARS INTERNATIONAL, INC.<br />
Sponsor Only ATOMEXPO<br />
218 BELGOPROCESS<br />
412 CANBERRA - AREVA<br />
214 CEA<br />
426 CONTAINER PRODUCTS CORPORATION<br />
130 DEWDROPS<br />
226 ENERGYSOLUTIONS<br />
131 FAYAT NUCLEAR<br />
Sponsor Only FLUOR GOVERNMENT GROUP<br />
118 GEOVARIANCES<br />
221 GNS GESELLSCHAFT FÜR NUKLEAR-SERVICE GmbH<br />
112 INTERA INCORPORATED<br />
119 ITECH-INSTRUMENTS<br />
413 JMCS SARL<br />
Sponsor Only KRAFTANLAGEN HEIDELBERG GmbH<br />
125 NUCLEAR RESEARCH & CONSULTING GROUP<br />
422 NUKEM TECHNOLOGIES GnbH<br />
230 NUVIA GROUP<br />
219 OECD NUCLEAR ENERGY AGENCY (NEA)<br />
424 ONET TECHNOLOGIES<br />
227 ORTEC (AMETEK SAS)<br />
126 PACTEC EPS LTD<br />
327 PORVAIR FILTRATION GROUP<br />
127 STUDSVIK SAS<br />
220 ROBATEL INDUSTRIES<br />
421 RÖHR + STOLBERG GmbH<br />
FRENCH NUCLEAR ENERGY SOCIETY (SFEN)<br />
133 SOCODEI<br />
117 TIB<br />
114 URS<br />
116 UTILIS SAS<br />
414 WESTINGHOUSE ELECTRIC COMPANY<br />
124 WSP ENVIRONMENT AND ENERGY
Exhibition Hours and Exhibitor Floorplan<br />
Exhibitors Listings in Numerical Order<br />
BOOTH COMPANY<br />
112 INTERA INCORPORATED<br />
114 URS<br />
116 UTILIS SAS<br />
117 TIB<br />
118 GEOVARIANCES<br />
119 ITECH-INSTRUMENTS<br />
124 WSP ENVIRONMENT AND ENERGY<br />
125 NUCLEAR RESEARCH & CONSULTING GROUP<br />
126 PACTEC EPS LTD<br />
127 STUDSVIK SAS<br />
130 DEWDROPS<br />
131 FAYAT NUCLEAR<br />
133 SOCODEI<br />
214 CEA<br />
217 ANDRA<br />
218 BELGOPROCESS<br />
219 OECD NUCLEAR ENERGY AGENCY (NEA)<br />
220 ROBATEL INDUSTRIES<br />
221 GNS GESELLSCHAFT FÜR NUKLEAR-SERVICE GmbH<br />
226 ENERGYSOLUTIONS<br />
227 ORTEC (AMETEK SAS)<br />
230 NUVIA GROUP<br />
320 ARS INTERNATIONAL, INC.<br />
327 PORVAIR FILTRATION GROUP<br />
412 CANBERRA - AREVA<br />
413 JMCS SARL<br />
414 WESTINGHOUSE ELECTRIC COMPANY<br />
421 RÖHR + STOLBERG GmbH<br />
422 NUKEM TECHNOLOGIES GnbH<br />
424 ONET TECHNOLOGIES<br />
426 CONTAINER PRODUCTS CORPORATION<br />
Sponsor Only ATOMEXPO<br />
Sponsor Only KRAFTANLAGEN HEIDELBERG GmbH<br />
Sponsor Only FLUOR GOVERNMENT GROUP<br />
ASME<br />
FRENCH NUCLEAR ENERGY SOCIETY (SFEN)<br />
39
ANDRA Booth: 217<br />
— SPONSOR —<br />
Contact: Gérald Ouzounian<br />
1/7, rue Jean-Monnet<br />
92298 Chatenay Malabry, Cedex<br />
France<br />
Email: International@andra.fr<br />
www.andra.fr<br />
Andra has developed a very significant experience in the field<br />
of management of radioactive waste, from initial design of<br />
repositories to their closure, including siting, designing and<br />
building of repositories, safety cases, waste acceptance and<br />
control, monitoring during operational and postclosure phases,<br />
and memory keeping. The agency has experience for managing<br />
for all types of radioactive waste, from sources to high level<br />
waste. The methods developed for managing waste include :<br />
establishing detailed inventories, with a prospective<br />
assessment, technical specifications for bids and contractors<br />
selection, disposal concepts development, specifications of the<br />
waste and their packaging (Waste Acceptance Criteria), design<br />
and construction of repositories, safety assessment and safety<br />
case, expertise and consultancy, including economic aspects<br />
and review of projects and of existing facilities.<br />
40<br />
ASME<br />
Contact: Vince Dilworth<br />
Phone: U.S./Canada: +1-800-843-2763<br />
Mexico: +001-800-843-2763<br />
Outside North America: +1-973-882-1170<br />
Fax: +1-973-882-1717<br />
Email: infocentral@asme.org<br />
www.asme.org<br />
ASME is a not-for-profit membership organization that enables<br />
collaboration, knowledge sharing, career enrichment, and skills<br />
development across all engineering disciplines, toward a goal<br />
of helping the global engineering community develop solutions<br />
to benefit lives and livelihoods. Founded in 1880 by a small<br />
group of leading industrialists, ASME has grown through the<br />
decades to include more than 120,000 members in over 150<br />
countries worldwide.<br />
From college students and early-career engineers to project<br />
managers, corporate executives, researchers and academic<br />
leaders, ASME's members are as diverse as the engineering<br />
community itself. ASME serves this wide-ranging technical<br />
community through quality programs in continuing education,<br />
training and professional development, codes and standards,<br />
research, conferences and publications, government relations<br />
and other forms of outreach.<br />
ARS INTERNATIONAL, INC. Booth: 320<br />
Contact: Virgene Mulligan,<br />
Vice President, Laboratory Services<br />
2609 North River Road<br />
Port Allen, LA, 70767 USA<br />
Phone: +1-800-401-4277<br />
Fax: +1-225-381-2996<br />
Email: marketing@amrad.com<br />
www.amrad.com<br />
ARS International, Inc. is a U.S. based, 8(a) Small Business<br />
specializing in the following services: Environmental<br />
Remediation Services; Analytical Services; Decontamination,<br />
Deactivation Demolition Services; Field Sampling Services;<br />
Disaster Response Services.<br />
ATOMEXPO<br />
— SPONSOR ONLY —<br />
Contact: Catherine Bulgachenko<br />
Phone: +7-495-663-38-21 (ext.152)<br />
Fax: +7-495-663-38-20<br />
Email: ESBulgachenko@atomexpo.com<br />
www.atomexpo.com
BELGOPROCESS Booth: 218<br />
Contact: Emmy Roos, Marketing and External Affairs<br />
Gravenstraat 73<br />
2480 DESSEL<br />
Belgium<br />
Phone: +32-14-33-40-08<br />
Fax: +32-14-33-40-99<br />
Email: emmy.roos@belgoprocess.be<br />
www.belgoprocess.be<br />
Founded in 1984, Belgoprocess is a limited liability company<br />
located in the Belgium nuclear area Mol-Dessel. Belgium has<br />
opted for a centralised processing and management of its<br />
radioactive waste, in which Belgoprocess plays a key role. The<br />
operational experience of Belgoprocess covers the<br />
decommissioning of nuclear facilities, including heavily alpha<br />
and/or beta/gamma-contaminated cells. Furthermore our<br />
competences cover the processing of radioactive waste by<br />
means of (super)compaction, incineration and waste water<br />
treatment, as well as specific processes and infrastructure<br />
developed for specific waste streams. In that perspective the<br />
general goal is to minimize the amount of radioactive waste<br />
produced, to maximise clearance of decontaminated material<br />
while optimising operational costs. Belgoprocess set-up a<br />
nuclear inventory management system supported by state of the<br />
art non-destructive radiological waste characterisation<br />
techniques. Currently over 50 000 drums of radioactive waste<br />
are stored at the Belgoprocess site, from low level waste up to<br />
high level vitrified waste. Belgoprocess offers cost effective<br />
solutions related to radioactive waste management and<br />
decommissioning projects.<br />
CANBERRA - AREVA Booth: 412<br />
Contact: Gerard Darmon, Regional Development Manager<br />
St-Quentin-en-Yvelines<br />
78180 Montigny-le-Bretonneux<br />
St-Quentin-en-Yvelines<br />
France<br />
Phone: +33-0-1-39-48-57-76<br />
www.canberra.com<br />
www.areva.com<br />
AREVA's CANBERRA brand incorporates a dozen<br />
manufacturing and sales operations worldwide. CANBERRA<br />
offers a wide range of measuring solutions for site safety and<br />
occupational safety. For 40 years, CANBERRA’s operations<br />
have been offering their expert services to the nuclear industry,<br />
to test laboratories and to scientific research operations. The<br />
AREVA Nuclear Measurement business unit designs and<br />
manufactures solutions meeting the various requirements of<br />
nuclear plant operators, including: • dosimetry and radiation<br />
protection, • servicing of reactor components, • monitoring of<br />
environmental impact, • materials inspection and access<br />
control, • waste management, • decontamination and<br />
dismantling operations. CANBERRA also provides fuel cycle<br />
laboratories and industries a comprehensive range of solutions,<br />
measuring devices and spectrometric analysis services.<br />
CEA Booth: 214<br />
Contact: Didier Dubot<br />
18, route du Panorama - BP N°6<br />
Fontenay-aux-Roses cedex 92265<br />
France<br />
Phone: +33-1-46-54-82-94<br />
Email: didier.dubot@cea.fr<br />
www.cea.fr<br />
The CEA is a key player in technological research and<br />
innovation in Europe and is active on the one hand in four<br />
major fields: energy, defence and global security, information<br />
technologies and health technologies, associated with<br />
fundamental research of excellence, and on the research<br />
infrastructures. The Clean-up Section (SAS) is a service of the<br />
CEA of Fontenay-aux-Roses made up of project managers<br />
which are specialized in one or several of its domains of<br />
expertise. Their goal is to manage and proceed to the<br />
remediation of nuclear sites, establish the radiological<br />
characterization of contaminated sites and manage and<br />
evacuate the nuclear waste due to the removal of the<br />
contaminated soils. The section may intervene at a national and<br />
an international level. Besides many publications, the Clean-up<br />
Site Section has developed a decontamination methodology to<br />
respond to the CEA centre’s need of dismantling all the nuclear<br />
facilities in order to set up buildings for new research activities.<br />
The goal of this methodology relies on various tools such as<br />
expertise vehicles with efficient detection performances<br />
(VEgAS), a recently developed software platform called<br />
Kartotrak and several modules aiming at sampling<br />
optimization, data analysis and geostatistical modeling, realtime<br />
monitoring and validation of clean up efficiency. These<br />
tools, used on the CEA centers, are a fitted and efficient answer<br />
to the various needs in radiological evaluation of contaminated<br />
sites and soils, concerning the optimization of the costs of<br />
measurements and clean-up process on one hand, and the waste<br />
volumes on the other hand.<br />
CONTAINER PRODUCTS Booth: 426<br />
CORPORATION<br />
Contact: John Hollinden, Consulting and Sales<br />
112 N. College Road<br />
Wilmington, NC 28495<br />
USA<br />
Phone: +1-910-382-6100<br />
Fax: +1-910-392-6778<br />
Email: john@c-p-c.com<br />
www.c-p-c.com<br />
Container Products Corporation has been in the business of<br />
supplying equipment and waste containers to the nuclear<br />
industry since 1981. We supply containers/packaging to the<br />
commercial nuclear world, Department of Energy Facilities,<br />
Department of Defense facilities, and Universities. We also<br />
have experience in design and manufacturing of hydraulic<br />
systems such as the box and drum compaction and<br />
decontamination units.<br />
Our products are also sold to Canadian nuclear power<br />
generation facilities and laboratories, and a number of foreign<br />
countries including Europe, the Far East (Korea, Japan), South<br />
America, (Argentina), Mexico, and Russia to name a few.<br />
Our container product line includes IP-1, IP-2, IP-3, Type A,<br />
(IAEA) and IATA containers in all shapes and sizes, with a<br />
wide range of payload, lift lug, fork pocket, safety arm, hinged<br />
lid and door options to meet most any customer needs.<br />
We feature a full Engineering Department with a PE on staff,<br />
and a QA Department with a NQA-1 program. We are also<br />
qualified to Canadian QA standards, ANSI/ASME standards<br />
and ISO 9001:2000.<br />
41
44<br />
F r om Nuclear P Proc<br />
essing t o Na tur e P<br />
reserve:<br />
Doing the R<br />
ight<br />
T hings R Right<br />
One of the world’s largest publicly traded engineering and construction<br />
companies, Fluor is recognized for completing complex projects on schedule and<br />
within budget.<br />
Fluor’s reputation as a leader in environmental management and radioactive<br />
waste management is well-established throughout the United States. Capitalizing<br />
on our global presence and environmental expertise, Fluor is positioned to<br />
deliver the same unparalleled level of service to our International clients, ensuring<br />
a sustainable future.<br />
We have the experience in project management, operations, and proven and<br />
emerging technologies to help our customers solve complex environmental<br />
management challenges.<br />
Safety, Performance, and Integrity<br />
Fluor Government Group<br />
2300 Clarendon Blvd., Suite 1110<br />
Arlington, Virginia 22201<br />
703.351.1204<br />
www.fluor.com<br />
© 2011 Fluor Corporation. All Rights Reserved. ADGV073011
DEWDROPS Booth: 130<br />
Contact: William Everett, President<br />
219, ave du Maréchal Leclerc<br />
Sin le Noble, 59450<br />
France<br />
Phone: +33-327-904-334<br />
Email: dewdrops@dewdrops.fr<br />
www.dewdrops.fr<br />
Dewdrops provides a flexible comprehensive on-site service to<br />
owners of wastes containing oils, solvents, organic cleaning<br />
fluids or foams. Our patented process and mobile treatment<br />
plants have been tailored to meet the exacting requirements of<br />
the nuclear industry. Dewdrops aims to play a key role in<br />
nuclear site value development by dealing economically and<br />
safely with sensitive organic liquide waste streams or arisings.<br />
ENERGYSOLUTIONS Booth: 226<br />
Contact: Pippa Waterman VP, Marketing & Communications<br />
Stella Building, Windmill Hill Business Park<br />
Swindon SN5 6NX<br />
United Kingdom<br />
Phone: +44-0-1793-733100<br />
Fax: +44-0-1793-733179<br />
Email: international@energysolutions.com<br />
www.energysolutions.com<br />
EnergySolutions, headquartered in Salt Lake City, Utah, is an<br />
international nuclear services company with operations<br />
throughout the United States, UK, mainland Europe, Canada<br />
and the Far East. In the UK we hold contracts with the Nuclear<br />
Decommissioning Authority to manage the UK’s Magnox<br />
reactor sites. We are a world leader focused on servicing the<br />
nuclear industry with the development and implementation of<br />
new technologies and approaches for resolving radioactive<br />
waste challenges faced by our clients.<br />
FAYAT NUCLEAR Booth: 131<br />
Contact: Henri Mydlarz<br />
3 rue René Razel<br />
Orsay Cedex 91892<br />
France<br />
Phone: +33-0-1-698-56915<br />
Email: hmydlarz@razel.fr<br />
www.fayat.com<br />
Founded in 1957, FAYAT is France’s leading family-owned<br />
Group in the sector of building and industry: 2.7 billion -<br />
turnover and more than 17 000 employees. With major<br />
industrial facilities in Europe, Asia and America, FAYAT<br />
regroups 118 autonomous subsidiaries in all the core<br />
businesses of building and public works, structural steel works,<br />
electricity, road building equipment, handling and hoisting<br />
equipment, and pressure vessels. Several FAYAT’s Group<br />
Companies have developed their activities in nuclear industry<br />
with two major projects currently in progress for CEA and<br />
EDF. RAZEL is a strong actor for civil works and turnkeys<br />
projects, BEC brings its specialties -core sampling and wire<br />
cutting- for dismantling in active zones, and COMETE<br />
supplies cranes and specialized equipment for nuclear plants<br />
and laboratories like EPR in France and China, or RJH test<br />
reactor. All these companies have their own design capacities<br />
and references. They can handle complex projects in<br />
partnership with any of the other Nuclear Industry actor.<br />
FLUOR GOVERNMENT GROUP<br />
— SPONSOR ONLY —<br />
Contact: Greg Meyer<br />
2300 Clarendon Blvd, Suite 1110<br />
Arlington, VA 22201<br />
Phone: +1-703-647-4340<br />
Fax: +1-703-469-1593<br />
Email: Greg.meyer@fluor.com<br />
Fluor is a global leader in engineering, procurement,<br />
construction, maintenance, and project management. Active<br />
across six continents, Fluor works with governments and multinational<br />
companies to design, build, and maintain many of the<br />
world's most complex and challenging capital projects. We are<br />
a solutions-based company with the technical expertise and<br />
financial strength to successfully complete the most difficult<br />
assignments. Fluor is recognized around the world as a firm<br />
that is reliable, delivers projects on time and within budget, has<br />
an outstanding safety record, and adheres to the highest ethical<br />
standards. Whether it's managing nuclear operations, cleaning<br />
out and tearing down nuclear facilities, or remediating a<br />
contaminated site, we bring leadership, experience, expertise,<br />
respect, and pride to every effort. Headquartered in Irving,<br />
Texas, Fluor is a FORTUNE 200 company and had revenues of<br />
$20.8 billion in 2010.<br />
FRENCH NUCLEAR ENERGY<br />
SOCIETY (SFEN)<br />
Contact: Bernard Jolly<br />
Phone: +33-0-1-53-58-32-10<br />
Fax: +33-0-1-53-58-32-11<br />
Email: sfen@sfen.fr<br />
www.sfen.org<br />
A forward-looking learned society with high-level exchanges<br />
on scientific and technical issues, organizing and sponsoring<br />
large national and international events. The SFEN provides a<br />
proactive and well-defined information policy thanks to its<br />
widespread international presence and cooperation agreements<br />
with learned nuclear societies.<br />
Founding member and one of the main promoters of the<br />
European Nuclear Society (ENS). Sustained contacts with<br />
institutions of the European Commission and with IAEA,<br />
working together with the French Atomic Forum and<br />
FORATOM. SFEN makes way for the young generation and<br />
transversal meeting groups open worldwide.<br />
45
GEOVARIANCES Booth: 118<br />
Contact: Jean-Jacques Peraudin, Sales Manager Environment<br />
49bis avenue Franklin Roosevelt<br />
AVON 77210<br />
France<br />
Phone: +33-1-6074-9090<br />
Fax: +33-1-6422-8728<br />
Email: bleines@geovariances.com<br />
www.geovariances.com<br />
GEOVARIANCES is a French independent software vendor<br />
which provides the most complete solution in Geostatistics:<br />
innovative methodologies, experts and software packages to<br />
answer challenges in mapping, volumes estimation, risk<br />
analysis. GEOVARIANCES develops and sells KARTOTRAK,<br />
the first all-in-one software solution designed for the<br />
radiological characterization of contaminated sites and<br />
facilities. KARTOTRAK provides an integrated workflow from<br />
in-situ characterization to final control after remediation.<br />
GEOVARIANCES also offers consulting and training services.<br />
GNS GESELLSCHAFT FÜR Booth: 221<br />
NUKLEAR-SERVICE GmbH<br />
Contact: Joerg Viermann<br />
Frohnhauser Str. 67<br />
45130 Essen<br />
Germany<br />
Phone: +49-201-109-0<br />
Email: info@gns.de<br />
www.gns.de<br />
Competence for Nuclear Services: GNS Gesellschaft für<br />
Nuklear-Service mbH, world leading supplier of casks for spent<br />
fuel, HLW and ILW, also offers services for management and<br />
disposal of spent fuel and all types of radioactive waste.<br />
More than one thousand spent fuel casks of the CASTOR® and<br />
CONSTOR® type and more than 5500 MOSAIK® casks for<br />
intermediate level waste make GNS mbH the supplier of the<br />
world’s top selling shielded transport and storage casks, which<br />
are today used in a number of countries on four continents.<br />
Design and supply of treatment facilities, decommissioning<br />
services and all kinds of engineering support round off our<br />
portfolio.<br />
INTERA INCORPORATED Booth: 112<br />
Contact: Mr. Benoît Paris<br />
90 Av. Lanessan<br />
69410 Champagne au Mont d'Or, France<br />
Phone: +33-0-4-37-49-13-30<br />
Email: bparis@intera.com<br />
Contact: Mr. Michael Apted<br />
3900 S. Wadsworth Blvd.<br />
Suite 555<br />
Denver, CO 80235, USA<br />
Phone: +1-303-985-0005<br />
Email: mapted@intera.com<br />
www.intera.com<br />
Established in 1974, INTERA has developed a solid track<br />
record of technical excellence and client satisfaction by<br />
providing innovative solutions to the environmental, waste<br />
isolation and natural resource management challenges facing<br />
industry and government.<br />
In each of these areas, INTERA brings unique and specialized<br />
experience that adds value to client projects. From restoring<br />
contaminated sites like former uranium mining and processing<br />
facilities, to developing innovative technologies to address<br />
complex environmental issues, such as the removal of<br />
chlorinated solvents from the subsurface, to using sophisticated<br />
numerical models to guide site investigation and remediation<br />
activities, INTERA is a leader in providing quantitative<br />
geosciences and engineering services to meet environmental<br />
challenges.<br />
Over the past 30 years, INTERA has served as a key<br />
contributor to high-profile underground storage projects. We<br />
have provided long-term support for nearly all of the high-level<br />
radioactive waste disposal programs in the U.S. and Canada,<br />
many programs in Europe, and several in Japan.<br />
Through this experience, our experts in hydrology,<br />
hydrogeology, geochemistry, civil and environmental<br />
engineering, reservoir engineering, applied statistics, and risk<br />
and decision analysis add value to all aspects of waste isolation<br />
and underground storage projects—from site characterization<br />
and process modeling to risk assessment and performance<br />
verification.<br />
Kraftanlagen Heidelberg:<br />
More than 40 years experience<br />
in nuclear engineering and construction<br />
Our services comprise of:<br />
• Radiation protection and dismantling of nuclear facilities<br />
• Radioactive waste management<br />
• Nuclear power plant technology<br />
• Plant design and process technology<br />
• Structural analysis and system engineering<br />
• Training and performance of high-quality welding<br />
For Kraftanlagen Heidelberg, customer focus means maintaining<br />
a permanent presence close to our clients, often directly,<br />
in nuclear power stations and research centers.<br />
Contacts:<br />
Heidelberg headquarters<br />
phone: +49 6221 94-07<br />
email: info@ka-heidelberg.de<br />
France offi ces in Manosque (ITER activities)<br />
and St. Genis-Pouilly (CERN activities)<br />
phone: +33 685986007<br />
email: Breton@ka-heidelberg.de<br />
www.ka-heidelberg.de<br />
47
48<br />
ITECH-INSTRUMENTS Booth: 119<br />
Contact: Marius Casile, General Manager<br />
ZI La Valampe - 3 av. de la Maranne<br />
Châteauneuf Les Martigues 13220<br />
France<br />
Phone: +33-4-42-07-4192<br />
Fax: +33-4-88-71-4200<br />
Email: info@itech-instruments.com<br />
www.itech-instruments.com<br />
ITECH-INSTRUMENTS is a French Company specialized in<br />
Nuclear Instrumentation. We develop our own Multi-channelanalyzers<br />
for NaI, LaBr3,CSI scintillators, Germanium or CZT<br />
semi-conductors. Our most famous analyzers are VENUS and<br />
ORION. All our electronics works with the most popular<br />
spectroscopic software INTERWINNER. ITECH-<br />
INSTRUMENTS can design and study your systems for wastedrums<br />
measurements, for in-situ measurements, for gloveboxes,...<br />
ITECH-INSTRUMENTS will supply, install and test<br />
the systems at your site or in our facility. We have Maintenance<br />
Service and Training Team. Keep free to contact us.<br />
JMCS SARL Booth: 413<br />
Contact: Jacques Minassian, General Manager<br />
8, Avenue Hoche<br />
Saint-Remy-Les-Chevreuse 78470<br />
France<br />
Phone: +33-0-13047-1552<br />
Email: jacquesminassian@orange.fr<br />
JMCS is a distributor selling a wide range of products for the<br />
nuclear industry, Alpha / Beta / Gamma equipments, Reactor<br />
Outage Service Cameras, Hardened Radiation Cameras, HPGe<br />
Spectrometer, Environmental Radiation Gamma Monitoring<br />
station, Phantom for Whole Body Counting system Companies<br />
represented: AHLBERG ELECTRONICS - ENVINET - LAB<br />
IMPEX - BSI - RSD.<br />
KRAFTANLAGEN HEIDELBERG GmbH<br />
— SPONSOR ONLY —<br />
Contact: Bernd Heinen<br />
Sales and Marketing<br />
Im Breitspiel 7<br />
69126 Heidelberg<br />
Phonee: +49-6221-94-1303<br />
Fax: +49-6221-94-41303<br />
Email: heinen@ka-heidelberg.de<br />
www.ka-heidelberg.de<br />
NUCLEAR RESEARCH & Booth: 125<br />
CONSULTING GROUP (NRG)<br />
Contact: Ronald Dekker & André Wakker<br />
NRG, P.O. Box 25<br />
1755 ZG, Petten<br />
The Netherlands<br />
Phone: +31-224-56-4234<br />
Email: radwaste@nrg.eu<br />
www.nrg.eu<br />
NRG Radiation & Environment is the innovative centre of<br />
excellence on radiological safety in the Netherlands. We can<br />
help you use nuclear technology safely and responsibly. NRG<br />
provides services internationally, supplying expertise and<br />
products to protect humans and the environment from the<br />
effects of radioactivity and radiation.<br />
During ICEM, NRG will present new methods for treatment of<br />
organic materials containing radioactive waste water, our waste<br />
management database REWIND to register waste in<br />
decommissioning projects, HIRARCHI a station to sort<br />
different waste levels, and our services regarding natural<br />
occurring radioactivity (NORM). We give you the full<br />
overview of services we offer in environmental remediation<br />
and radioactive waste management.<br />
Our radiological protection experts provide services for:<br />
• National and international public authorities<br />
• Utilities<br />
• Pharmaceutical and medical sector<br />
• Oil and gas producers<br />
• Scrap, ore and metal processing companies<br />
• Airlines<br />
Our expertise and services cover the entire spectrum of<br />
radiological protection:<br />
• Laboratory analysis and monitoring equipment/networks<br />
• Dosimetry and calibration services, personal dosimetry<br />
• Advisory services and license application support<br />
• Risk assessment, environmental impact reports and policy<br />
support<br />
• Support, auditing and optimization of operations<br />
• Training<br />
• Ageing management and/or dismantling of radiological<br />
facilities<br />
• Clean-up, decontamination and recycling, waste disposal<br />
and site declassification.
NUKEM TECHNOLOGIES Booth: 422<br />
GmbH<br />
Contact: Beate Scheffler,<br />
Director Communications & Support Services<br />
Industriestr. 13<br />
Alzenau 63755<br />
Germany<br />
Phone: +49-623-9104<br />
Fax: +49-6023-911188<br />
Email: info@nukemtechnologies.de<br />
www.nukemtechnologies.de<br />
NUKEM Technologies GmbH world-wide offers nuclear<br />
engineering solutions: • Management of radioactive waste<br />
(from concept development to turn-key delivery of complete<br />
waste treatment centers, techniques for all types of radioactive<br />
waste) • Spent Fuel Management (storage technologies,<br />
handling facilities, technologies for characterization of spent<br />
fuel elements) • Decommissioning of nuclear facilities (from<br />
concept development to complete project management, broad<br />
spectrum of techniques for dismantling and decontamination) •<br />
Comprehensive spectrum of engineering and consulting<br />
services.<br />
������������������������������������������������������������<br />
����������������������������������������������������������������<br />
�������������������������������������<br />
���������������������<br />
�����������������������������������<br />
���������������������������������<br />
�����������������������������������������������������������<br />
�������������������������<br />
����������������<br />
���������������<br />
��������������������<br />
������������������������<br />
�������������������������<br />
����������������������������������<br />
����������������������������<br />
������������������������������������<br />
������������������������������<br />
����������������������<br />
������������������������������������<br />
���������������������������������<br />
���������������������������������������������������������������<br />
������������������������������<br />
�����������������������������������������������<br />
������������������������������������������������<br />
NUVIA GROUP Booth: 230<br />
Contact: Ron Smith, International Sales Manager<br />
Kelburn Court, Daten Park, Risley<br />
Warringdon, Cheshire, WA3 6TW<br />
United Kingdom<br />
Phone: +44-0-1925-858200<br />
Fax: +44-0-1925-811867<br />
Email: info@nuvia-group.com<br />
www.nuvia-group.com<br />
The Nuvia Group delivers to its clients a unique range of<br />
vertically integrated solutions covering nuclear new build,<br />
plant life extension, operations, radiation safety,<br />
decommissioning and waste management. With a total staff of<br />
over 1,000 it brings together the nuclear experience and<br />
expertise of Nuvia Limited in the UK and Nuvia France with<br />
its subsidiaries NTS, Salvarem, Mecatiss, Millennium, Essor<br />
and Vraco as well as its international operations Nuvia India,<br />
Nuvia Italy and Nuvia Nordic.<br />
OECD NUCLEAR ENERGY Booth: 219<br />
AGENCY (NEA)<br />
Contact: OECD Nuclear Eneregy Agency (NEA)<br />
12 boulevard des îles<br />
Issy-les-Moulineaux 92130<br />
France<br />
Phone: +33-01-45-24-1015<br />
Email: nea@oecd-nea.org<br />
www.oecd-nea.org<br />
The Nuclear Energy Agency (NEA) is a specialised agency of<br />
the Organisation for Economic Co-operation and Development<br />
(OECD). Its 30 member countries account for approximately<br />
85% of global installed nuclear energy capacity and represent<br />
the world?s best nuclear expertise. NEA studies are carried out<br />
in the areas of nuclear safety and regulation, radioactive waste<br />
management, radiological protection and public health, nuclear<br />
science and data, nuclear development and the fuel cycle, and<br />
legal affairs. For more information see: www.oecd-nea.org.<br />
ONET TECHNOLOGIES Booth: 424<br />
— SPONSOR —<br />
Contact: Philippe Gros Gean,<br />
Business Development Director,<br />
Gwenaëlle Gozé, communication officer<br />
Phone: +33-4-91-29-18-44 or +33-4-91-29-18-74<br />
Email: pgrosgean@onet.fr or ggoze@onet.fr<br />
www.onet-technologies.com<br />
In a nut shell:<br />
• Turnover: € 225 Million<br />
• 2 300 employees<br />
• 600 engineers & experts, 1 700 operators, technicians and<br />
specialized site workers<br />
• 438 employees recruited in 2010<br />
• 3% of the turnover for R&D<br />
Our core Business:<br />
• Engineering & site services for nuclear power plants and<br />
nuclear installations<br />
• Decommissioning, decontamination & waste management<br />
• New build<br />
• Training<br />
Our international network includes:<br />
Subsidiaries in Bulgaria, India, Italy, Romania, United<br />
Kingdom… and partners all over the world.<br />
49
ONET TECHNOLOGIES is part of the ONET group, a<br />
service provider with a turnover of €1.4 Billion<br />
• 57 000 employees<br />
• Service provider through 4 trademarks:<br />
- ONET TECHNOLOGIES: nuclear engineering and<br />
services<br />
- ONET PROPRETE MULTISERVICES: cleaning<br />
and associated services<br />
- ONET SECURITE: guarding, electronic security<br />
- AXXIS RESSOURCES: recruitment, temporary labour<br />
ORTEC (AMETEK SAS) Booth: 227<br />
Contact: Reginald Recco, Sales Manager<br />
Elancourt 78990<br />
France<br />
Phone: +33-0-1-3068-89-10<br />
Fax: +33-0-1-30-68-89-99<br />
Email: reginald.recco@ametek.com<br />
www.ortec-online.com<br />
ORTEC is a leading global manufacturer of radiation detection<br />
instrumentation offering solutions for NDA, and Waste Assay<br />
applications including instrumentation for mobile gamma ray<br />
assays of sites, surfaces and objects. Visit our booth to demo<br />
the micro-trans-spec portable HPGe gamma spectrometer.<br />
PACTECH EPS LTD. Booth: 126<br />
Contact: Mike Nichols, Managing Director<br />
Buttermere Pavilion, Ingwell Drive<br />
Westlakes Science & Technology Park<br />
Cumbria CA24 3JZ<br />
United Kingdom<br />
Phone: +44-0-1946-695005<br />
Email: mikenichols@pactecinc.com<br />
www.pacteceps.co.uk<br />
PacTec, Inc. has over 20 years experience in manufacturing a<br />
complete line of custom engineered packaging products for the<br />
nuclear waste, hazardous waste, and transportation industries.<br />
We manufacture soft sided packaging such as IP-1 and IP-2 lift<br />
bags which meet IAEA requirements, LSA and SCO wraps,<br />
and rail car liners and tarps. PacTec has been awarded 9<br />
patents, and is ISO 9001-2008 certified. We also provide<br />
product testing and development, working with our UK clients<br />
such as LLWR, RSRL, Magnox, Dounreay, and Sellafield.<br />
PORVAIR FILTRATION GROUP Booth: 327<br />
Contact: Chris Chadwick<br />
1 Concorde Close<br />
Fareham, Hampshire PO15 5RT<br />
United Kingdom<br />
Phone: +44-0-1489-864330<br />
Fax: +44-0-1489-864399<br />
Email: info@porvairfiltration.com<br />
www.porvairfiltration.com<br />
Porvair Filtration Group is an international leader in the design<br />
and supply of high quality filtration and separation materials<br />
and products. As an engineering company we offer fully<br />
optimised solutions to the nuclear industry including the power<br />
generation, fuel production, reprocessing, decontamination and<br />
waste packaging sectors. We provide everything from a single,<br />
specialised, retrofit element to a complete packaged system<br />
meeting the precise needs of complex applications, together<br />
with on-site support and a complete after sales service.<br />
50<br />
ROBATEL INDUSTRIES Booth: 220<br />
Contact: Christophe Bruneel, Business Manager<br />
Rue de Genève - B.P. 203<br />
GENAS Cedex 69741<br />
France<br />
Phone: +33-0-4-72-22-10-10<br />
Fax: + 33-0-4-78-90-23-79<br />
Email: commercial@robatel.fr<br />
www.robatel.fr<br />
ACTIVITIES - Turnkey contractor for major nuclear projects :<br />
design, manufacture, and assembly of shielded laboratories for<br />
research or production, decontamination facilities, waste<br />
packaging facilities, nuclear fuel production, and testing<br />
installations using glove-box technology - Design, certification<br />
and manufacture of type B casks for transportation and storage<br />
of radioactive materials (fuel, waste, sources): 73 type B casks<br />
- Process equipment for reprocessing facilities -<br />
Decommissioning projects - Development and production of -<br />
special equipment - for the nuclear industry.
RÖHR + STOLBERG GmbH Booth: 421<br />
Contact: Frank Köhler<br />
Bruchfeld 52<br />
Krefeld<br />
Germany<br />
Phone: +49-2151-5892-50 or<br />
+49-170797-8939 (Mobile)<br />
Email: frank.koehler@roehr-stolberg.de<br />
www.roehr-stolberg.de<br />
Calder Group is a pan-European engineering group, active in<br />
lead engineering and the manufacture and distribution of lead<br />
sheet. Calder is leading manufacturer of radiation shielding.<br />
Calder Companies provide radiation shielding products,<br />
services and solutions meeting customer demands for<br />
applications in the nuclear power and nuclear healthcare<br />
industry.<br />
SOCODEI Booth: 133<br />
Contact: Christophe Maufrais<br />
Phone: +33-0-4-66-50-5987<br />
Email: christophe.maufrais@socodei.fr<br />
www.socodei.fr<br />
SOCODEI is the French leader for short half life radioactive<br />
waste treatment by incineration and melting.<br />
STUDSVIK SAS Booth: 127<br />
Contact: Thierry Hoffmann<br />
Centre d’Affaires Euripole<br />
ZA des Vauguillettes III – 89100 SENS<br />
France<br />
Phone: +3-86-66-60-75<br />
Email: info@studsvik.fr<br />
www.studsvik.com<br />
MAIN ACTIVITIES - Services on the Nuclear Field :<br />
• Processing of radioactive waste<br />
• On-site waste services<br />
• Engineering and consultancy<br />
• Health physics services (manufacture and montage)<br />
• Transport logistics<br />
• Decommissioning services (engineering and operating)<br />
• Operational and outage support (decontamination, nuclear<br />
logistic)<br />
• Fuel and materials performance<br />
• Materials integrity and water chemistry<br />
• Nuclear fuel analysis software<br />
• Design and built<br />
TIB Booth: 117<br />
Contact: Patrick Poitevin<br />
32 rue de Saint-Rémy<br />
Brezolles 28270<br />
France<br />
Email: p.poitevin@tib.fr<br />
Please visit our booth for more information about our services<br />
and products.<br />
URS Booth: 114<br />
— SPONSOR —<br />
Contact: Daniel Curry<br />
Email: Daniel.Curry@wsms.comwww.urscorp.com<br />
URS Corporation is a leading provider of engineering,<br />
construction and technical services around the world.<br />
Headquartered in San Francisco, the company operates in 45<br />
countries with approximately 55,000 employees providing<br />
services to federal, state and local governmental agencies as<br />
well as private clients in the Energy, Industrial and<br />
Infrastructure sectors.<br />
URS Corp has particular expertise in environmental<br />
management and operation of nuclear facilities on behalf of the<br />
United States government and is the market leader in nuclear<br />
waste management, disposal and clean-up. It has one of the<br />
best overall safety records in the US nuclear industry and since<br />
1999 has brought this track record and capability to nuclear<br />
waste programmes in the UK.<br />
URS leads the two consortia: UK Nuclear Waste Management<br />
Ltd, and Nuclear Management Partners Ltd which were<br />
successful in winning the management and operations contracts<br />
with the UK Nuclear Decommissioning Authority for the Low<br />
Level Waste Repository and Sellafield Sites respectively.<br />
UTILIS SAS Booth: 116<br />
Contact: Pascal Maloni, Sales Manager<br />
ZAC Eurotransit - rue Mariotte<br />
Ennery 57365<br />
France<br />
Phone: +33-0-87-74-60 74<br />
Fax: +33-0-3-87-71-07-60<br />
Email: contact@utilis.fr<br />
www.utilis.fr<br />
For more than 10 years UTILIS SAS has been manufacturing<br />
rapid-deploy shelters and designing expeditionary systems for<br />
protection of people and operational equipment. Thanks to a<br />
large range of soft-wall and hard-wall shelters UTILIS SAS<br />
meets requirements of both military, civil and homeland<br />
security markets and has a history of complete equipment<br />
solutions for various applications:<br />
• Camps / Command Posts / Head Quarters<br />
• CBRN decontamination of people<br />
• CBRN collective protection<br />
• CBRN protection for vehicles / trucks / helicopters / tanks<br />
• Rapid deploy hangars for maintenance of aircrafts or<br />
vehicles<br />
• Field hospitals / First-aid Medical Posts<br />
We offer field-proven and reliable products that meet NATO<br />
and MIL-standard specifications and occupy a unique position<br />
in the market place. Our shelter systems have successfully<br />
passed snow load, solar resistance, blackout, wind, wind driven<br />
rain resistance and durability tests at the Aberdeen Proving<br />
Grounds (U.S. Army). To enhance your mission capabilities, a<br />
quick and efficient service support is provided via our<br />
international presence with head offices in Europe, US, Latin<br />
America, Middle East and Asia.<br />
51
URS has developed proven Integrated Management Systems that create safety conscious cultures for the highest hazard,<br />
most complex and regulated facilities in the world. With our extensive resources, customers receive the most<br />
comprehensive inventory of engineering, construction and management available.<br />
The Global Management & Operations Services Group of URS provides safe, innovative management of high risk,<br />
technically complex projects, programs and facilities for the U.S. Department of Energy and other global organisations.<br />
Nuclear Processing/High Hazard Facilities<br />
URS is a leader in the safe operation of high-hazard/high-consequence facilities. We have safely operated plutonium and<br />
other complex nuclear chemical processing facilities at DOE sites across the US.<br />
URS is part of each of the consortiums that have been awarded contracts to manage and operate the UK’s Low Level<br />
Waste Repository and Sellafield sites by the Nuclear Decommissioning Authority.<br />
Nuclear/Hazardous Waste<br />
As the only company to vitrify high-level radioactive nuclear waste in the United States, URS is a world leader in safely<br />
managing nuclear and other hazardous wastes for a wide range of federal and state agencies.<br />
URS is the only DOE contractor successfully to licence a deep geological nuclear waste repository in the U.S. The company<br />
oversaw the building, licensing and start up of the DOE’s Waste Isolation Pilot Plant, a transuranic waste repository near<br />
Carlsbad, New Mexico.<br />
Additionally, URS was the lead managemnt contractor for the licensing of Yucca Mountain.<br />
Environmental/Facility Closure<br />
URS is a leader in the safe and regulatory compliant closure of facilities formerly used to process and store nuclear and<br />
other hazardous materials. URS capitalises on state-of-the-art technical knowledge backed by six decades of experience<br />
working at nuclear facilities for commercial and government clients.<br />
URS’s closure efforts are backed by experienced teams of professional engineers, scientists, regulatory analysts and<br />
project managers specialising in hazardous and radiological waste engineering; soil, groundwater and mixed waste<br />
remediation; facility decontamination and decommissioning; and environmental compliance.<br />
Global Environmental Technology<br />
URS has a proud history of providing advanced technological solutions. URS is a leader in the development of innovative<br />
technologies to provide solutions to problems ranging from environmental remediation to homeland security. These<br />
technologies range from solvent cleanup methods to waste site capping and sealing approaches.<br />
URS also pioneered a variety of natural remedies such as phytoremediation (using natural vegetative processes),<br />
bioremediation (using naturally occurring microbes), and monitored natural remediation (establishing a groundwater<br />
mixing zone), to passively remove contaminants and improve the cost and effectiveness of its cleanup efforts.<br />
53
54<br />
FOR A HEALTHY ENVIRONMENT,<br />
Westinghouse is<br />
focused on<br />
nuclear technology.<br />
Westinghouse Electric Company is contributing to a healthy environment<br />
as it builds new nuclear power plants that emit zero greenhouse gases when<br />
generating electricity. Our dedication to a cleaner environment extends to<br />
servicing existing nuclear power plants and managing by-products in an<br />
environmentally responsible manner.<br />
Westinghouse provides comprehensive integrated services and solutions<br />
to the Decommissioning and Dismantling (D&D) and Waste Management<br />
industries. We have acquired extensive experience in the dismantling of<br />
nuclear installations from uranium mills to nuclear power plants.<br />
We provide state-of-the-art solutions for the treatment and handling<br />
of radioactive waste. And we offer proven solutions for the storage of<br />
low-, intermediate- and high-level waste.<br />
Westinghouse technology will help provide future generations with safe,<br />
clean and reliable electricity.<br />
Check us out at www.westinghousenuclear.com.
WESTINGHOUSE Booth: 414<br />
ELECTRIC COMPANY<br />
— SPONSOR —<br />
Contact: Joseph Boucau, Director,<br />
Global D&D and Waste Management<br />
43, rue de l’Industrie<br />
Nivelles 1400<br />
Belgium<br />
Phone: +32-67-28-84-34<br />
Fax: +32-67-28-8534<br />
Email: boucauj@westinghouse.com<br />
www.westinghouse.com<br />
Westinghouse Electric Company is a leading provider of fuel,<br />
services, technology, plant design and equipment to utility and<br />
industrial customers globally in the commercial nuclear electric<br />
power industry. Nearly 50% of all commercial nuclear power<br />
plants in operation worldwide, and approximately 60% in the<br />
U.S., are based on Westinghouse technology. Westinghouse<br />
supplied the original equipment design for 62 out of the 104<br />
licensed commercial nuclear reactors in the U.S. and 113 out of<br />
the 443 licensed commercial nuclear reactors worldwide.<br />
Westinghouse provides global, operationally excellent nuclear<br />
services that keep operating plants operating safely and<br />
efficiently, as well as comprehensive, integrated services and<br />
solutions in support of decommissioning and dismantling<br />
(D&D) and waste management.<br />
WSP ENVIRONMENT Booth: 124<br />
AND ENERGY<br />
Contact: Peter Booth<br />
The Victoria 150-182<br />
Salford Quays<br />
M50 3SP Manchester<br />
United Kingdom<br />
Phone: +44-16-1886-2401<br />
Email: peter.booth@wspgroup.com<br />
www.wspenvironmental.com<br />
WSP Environment and Energy is a global business and part of<br />
the WSP Group building on a sound platform supporting the<br />
nuclear and radiological sectors. We are supporting our clients<br />
in the areas of radioactive waste management, environmental<br />
remediation, dose and risk assessment, stakeholder<br />
engagements, EIA and decision making processes. Drawing on<br />
the expertise held within WSP and our delivery partners we can<br />
provide these services across the entire nuclear fuel cycle and<br />
NORM related industries.<br />
Notes<br />
55
Session 1 Abstracts<br />
ICEM'11 Abstracts - Per instructions, only the first 200 words of each abstract is shown.<br />
SESSION 1 — PLENARY SESSION<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 2 — PANEL: APPROACHES FOR INTERNATIONAL COLLABORATION (5.18)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 3 — PANEL: LESSONS LEARNED: FUKUSHIMA, CHERNOBYL-<br />
25 YEARS LATER, TMI-2 & OTHER EXPERIENCES (3.11)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 4 — NATIONAL AND INTERNATIONAL PROGRAMS FOR L/ILW MANAGEMENT (1.2)<br />
1) LOW LEVEL WASTE DISPOSAL REGULATORY ISSUES IN THE US (w/oP-59311)<br />
David James, Thomas Kalinowski, DW James Consulting LLC; Lisa Edwards, Electric Power Research Inst. (USA)<br />
The United States led the international efforts to define disposal requirements for low level radioactive wastes with the publication<br />
of US Regulations governing the disposal of such wastes. The requirements were based on a system of waste classification<br />
based on the concentrations of certain radionuclides considered problematic for the protection of future generations from radiation<br />
exposure. The regulation, itself, was based on a process for the development of new disposal sites defined by the US congress to<br />
provide an equitable distribution of burden to various regions of the US. This process has met with little success in the almost 30<br />
years since its initiation leaving only an incomplete patchwork of disposal options which are primarily dependant on the same<br />
options that existed before the act and regulations were initiated. There is currently a new focus on the basis for some of the regulatory<br />
requirements derived from advances in the understanding of dose impacts from certain radionuclides, improvements in performance<br />
assessment methodologies, the increased use of engineered barriers, the reality of current disposal economies, along with<br />
the failure of the act to conform to expectations. This paper will provide an update on the discussion taking place with a focus on<br />
the technical considerations.<br />
2) TAKING THE UK’S NATIONAL LLW PROGAMME FROM STRATEGY<br />
DEVELOPMENT TO IMPLEMENTATION (w/oP-59059)<br />
David Rossiter, Rachel O’Donnell, LLW Repository Ltd. (UK)<br />
In 2008 UK Nuclear Waste Management Ltd (UKNWM) became the Parent Body Organisation (PBO) at the Low Level Waste<br />
Repository (LLWR) in the UK. LLWR is the primary disposal facility for the UKs LLW, supporting a wide range of industries<br />
across the nuclear power generation, reprocessing, defence, healthcare, education, and oil and gas sectors. One of the key tasks following<br />
the appointment of the new PBO was to work with the Nuclear Decommissioning Authority (NDA) to develop a national<br />
strategy for LLW generated in the UK, predominantly in the NDA estate. The new National Strategy for LLW was required to<br />
address the gap between the forecast waste arisings and predicted capacity at LLWR.<br />
The National Strategy for LLW Management was published in August 2010 following an 18 month development period. The<br />
main focus of the strategy is on three areas:<br />
• Application of the waste management hierarchy to extend the life of LLWR and ensure waste is managed in a risk-based,<br />
fit-for-purpose manner<br />
• Making best use of existing assets such as transport, packaging, treatment and disposal facilities<br />
• Opening up new fit-for-purpose waste management routes to divert waste away from LLWR<br />
Developing a robust strategy is vital to provide…<br />
3) CEA’S WASTE MANAGEMENT POLICY AND STRATEGY. LESSONS LEARNED (w/oP-ICEM2011-59201)<br />
Didier Dall’ava, CEA (France)<br />
Radioactive wastes are generated during operation as well as during the decontamination and dismantling of CEAs nuclear<br />
facility/installation. The safe and responsible management of radioactive wastes at all stages is an essential requirement of the regulatory<br />
system. The management covers the whole sequence of operations starting with the generation of waste and ending with its<br />
disposal. The disposal here means discarding of waste with no intention for retrieval.<br />
It is important to note here that the safety principles and practices that are applicable during the operational phase are also applicable<br />
during the decommissioning phase. As the radioactive waste arising is an inevitable outcome of decommissioning work, all<br />
the regulatory requirements associated with decommissioning remain in force in waste management. This presentation deals initially<br />
with the regulatory standards related to the management of wastes. As the management of radioactive wastes inevitably<br />
includes treatment and conditioning of wastes, following treatment and conditioning of wastes, storage, transportation and eventual<br />
disposal are the logical outcome of the radioactive wastes, processes are at any time improved based on the feedback experience<br />
and the lessons learned.<br />
4) REGULATIONS FOR THE DISPOSAL OF RADIOACTIVE WASTE IN<br />
THE KONRAD REPOSITORY(w/oP-ICEM2011-59105)<br />
Hagen Gunther Jung, Lower Saxony Water Management, Coastal Protection and Nature Conservation Agency<br />
(NLWKN); Gabriele Bandt, TÜV Nord EnSys Hannover GmbH & Co. KG (Germany)<br />
The German Atomic Act required a plan approval process to grant the license for the construction and operation of the Konrad<br />
repository for radioactive waste with negligible heat generation (nearly analog to low/intermediate level waste).<br />
56
Abstracts Session 4<br />
In 2002 the Ministry for Environment of the federal State of Lower Saxony licensed the construction and operation of the Konrad<br />
repository. In addition to the Plan Approval License a Water Law Permit is required for the operation of the repository. It considers<br />
the impact of radioactive as well as non-radioactive harmful substances on the near-surface groundwater. The Water Law Permit<br />
limits the total maximum masses, which are allowed for the Konrad repository.<br />
According to the Water Law Permit the operator of the repository has to register the radioactive and non-radioactive harmful<br />
substances and to balance them. Thus, the Federal Office for Radiation Protection (BfS) as the permit holder had to develop a concept<br />
accordingly. BfS defined threshold values for registering and balancing the harmful substances, which led to a site specific<br />
solution for the Konrad repository.<br />
The Lower Saxony Water Management, Coastal Protection and Nature Conservation Agency (NLWKN) as the responsible<br />
water law regulatory authority examined this concept in order to exclude an adverse…<br />
5) THE HYDROGEOLOGIC ENVIRONMENT FOR A PROPOSED DEEP GEOLOGIC REPOSITORY<br />
IN CANADA FOR LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTE (w/oP-59285)<br />
Jonathan Sykes, Stefano Normani, Yong Yin, University of Waterloo;<br />
Mark Jensen, Nuclear Waste Management Organization (Canada)<br />
A Deep Geologic Repository (DGR) for low and intermediate level radioactive waste has been proposed by Ontario Power<br />
Generation for the Bruce nuclear site in Ontario, Canada. The DGR is to be constructed at a depth of about 680 m below ground<br />
surface within the argillaceous Ordovician limestone of the Cobourg Formation. This paper describes the hydrogeology of the DGR<br />
site developed through both site characterization studies and regional-scale numerical modelling analysis. The analysis provides a<br />
framework for the assembly and integration of the site-specific geoscientific data and explains the factors that influence the predicted<br />
long-term performance of the geosphere barrier. Flow system evolution was accomplished using both the density-dependent<br />
FRAC3DVS-OPG flow and transport model and the two-phase gas and water flow computational model TOUGH2-MP. In the geologic<br />
framework of the Province of Ontario, the DGR is located at the eastern flank of the Michigan Basin. Borehole logs covering<br />
Southern Ontario combined with site specific data from 6 deep boreholes have been used to define the structural contours and<br />
hydrogeologic properties at the regional-scale of the modelled 31 sedimentary strata that may be present above the Precambrian<br />
crystalline basement rock. The regional-scale domain encompasses an 18,500 km2 region extending from…<br />
6) RADIOACTIVE WASTE MANAGEMENT CHALLENGES AND PROGRESS IN IRAQ (wP-59164)<br />
Fouad Al-Musawi, Emad Shamsaldin, Ministry of Science & Technology (Iraq);<br />
John Cochran, Sandia National Laboratories (USA)<br />
The government of Iraq, through the Ministry of Science and Technology (MoST) is decommissioning Iraqs former nuclear<br />
facilities. The 18 former facilities at the Al Tuwaitha Nuclear Research Center near Baghdad include partially destroyed research<br />
reactors, a fuel fabrication facility and radioisotope production facilities. These 18 former facilities contain large numbers of silos<br />
and drums of uncharacterized radioactive waste and approximately 30 tanks that contain or did contain uncharacterized liquid<br />
radioactive wastes. Other key sites outside of Al Tuwaitha include facilities at Jesira (uranium processing and waste storage facility),<br />
Rashdiya (centrifuge facility) and Tarmiya (enrichment plant).<br />
The newly created Radioactive Waste Treatment Management Directorate (RWTMD) within MoST is responsible for Iraqs<br />
centralized management of radioactive waste, including safe and secure disposal. In addition to being responsible for the uncharacterized<br />
wastes at Al Tuwaitha, the RWTMD will be responsible for future decommissioning wastes, approximately 900 disused<br />
sealed radioactive sources, contaminated debris from the first Gulf War in 1991 and unknown quantities of NORM wastes from oil<br />
production in Iraq.<br />
This paper presents the challenges and progress that the RWTMD has made in setting-up a radioactive waste management program.<br />
The progress includes the establishment of a staffing structure, staff, participation in international…<br />
SESSON 5 — L/ILW TREATMENT TECHNOLOGY DEVELOPMENT AND IMPLEMENTATION (1.15)<br />
1) RESEARCH AND TECHNOLOGY DELIVERY AT SELLAFIELD, UK (w/oP-59372)<br />
Mike James, Sellafield Ltd (UK)<br />
This paper provides an overview of research and development which is critical to the successful delivery of our operational<br />
and clean up activities. Today we operate a number of plants supporting the nuclear fuel cycle including two reprocessing plants,<br />
fuel fabrication and associated waste management plants for low, intermediate and high level wastes. Our decommissioning programme<br />
is extensive with challenging and complex programmes of work along side the operational facilities. This involves a prioritised<br />
programme to reduce risk and hazard in former reprocessing and fuel fabrication plants, fuel storage ponds and waste silos<br />
and other related facilities.<br />
Our work covers the span of research, development and technology transfer from investigations into low maturity applications<br />
through to deployment of mature technologies across a range of operational and decommissioning areas. An over view of this will<br />
be provided through examples. Characterisation is one of the key areas for successful operations in the nuclear industry today. Our<br />
work has included commissioning work through others such as the National Nuclear Laboratory to investigate novel technologies<br />
such as the use of muon tomography and implementing HiRad a high radiation field detector. Our work does not just include investment<br />
in novel applications a number of significant…<br />
57
Session 5 Abstracts<br />
2) WASTE LOADING ENHANCEMENTS FOR HANFORD LAW GLASSES (wP-59018)<br />
Albert Kruger, US Department of Energy WTP Engineering Division (USA)<br />
About 50 million gallons of mixed waste is currently stored in underground tanks at The United States Department of Energys<br />
(DOE) Hanford site in Washington state. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOEs<br />
Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will<br />
be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity<br />
Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product is destined for disposal in an engineered<br />
facility at Hanford site while the IHLW product will be disposed in a national geological repository. Both waste forms must meet<br />
a variety of requirements to ensure the protection of the environment before they can be accepted for disposal.<br />
DOE-WTP is examining options to optimize the LAW Facility and LAW glass waste form. One option under evaluation is to<br />
enhance the waste processing rate of the vitrification plant currently under construction. It is likely that the capacity of the LAW<br />
vitrification plant can be increased incrementally by implementation of a variety of low-risk, high-probability changes, either separately<br />
or in combination. These changes include:…<br />
3) THOR(R) STEAM REFORMING TECHNOLOGY FOR THE TREATMENT<br />
OF COMPLEX AND PROBLEMATIC WASTES (wP-59084)<br />
J. Brad Mason, Adam L. Foster, Studsvik, Inc.(USA)<br />
Many types of complex radioactive wastes exist that, due to their chemical and radiological characteristics, are problematic to<br />
treat using traditional methods. Studsvik has developed the THOR® process that has the capability to successfully treat a wide variety<br />
of radioactive wastes including those with high organic content, high nitrate and nitrite content, high solids content, and heavy<br />
metal bearing. The process produces a dry stable waste form with no liquid effluents and environmentally compliant off-gas emissions,<br />
while reducing the overall waste volume.<br />
The more than 10 years of successful operations at Studsviks Processing facility in Erwin, TN USA provides the foundation<br />
for the deployment of the THOR® steam reforming process for the treatment of many complex wastes. The THOR® process has<br />
been shown to effectively convert numerous types of U.S. Department of Energy (DOE) liquid radioactive wastes into solid products<br />
while providing a final waste form with properties comparable to vitrified glass waste forms. In addition to testing and ongoing<br />
project work in the U.S., multiple test programs including lab-scale and engineering-scale demonstrations have been successfully<br />
completed for several international organizations. This international work has included testing and development work with<br />
solid and liquid organic wastes, as well as high…<br />
4) A ROOM TEMPERATURE STABILIZATION AND WASTE VOLUME REDUCTION METHOD<br />
TESTED ON BELGIAN INTERMEDIATE-LEVEL HOMOGENEOUS<br />
BITUMINIZED WASTE (EUROBITUM) (wP-59103)<br />
Nathalie R.E.N. Impens, SCK-CEN; Jan Deckers, BelgoProcess; Lesley Adriaensen,<br />
Pierre Van Iseghem, Studiecentrum voor Kernenergie-Centre d’Etude de l’Energie Nucléaire (Belgium)<br />
We developed a room temperature method to recondition intermediate-level homogeneous bituminized waste, called Eurobitum.<br />
Using this method, Eurobitum could be separated in an aqueous and an organic effluent, and a solid asphaltene-salt mix. In<br />
this paper, we present the results of the room temperature reconditioning method using real radioactive Eurobitum samples. The<br />
dissolution and separation processes were optimized. The residual waste could then be pressed towards a material, that might be<br />
suitable for geological disposal. The concentration of radionuclides in the two secondary waste effluents was thereafter determined.<br />
The aqueous effluent contained radionuclide concentrations below the treatment levels for common radioactive waste water treatment<br />
processes, whereas the alpha radioactivity of the organic phase was low enough to consider the possibility to inject it into the<br />
CILVA radwaste incinerator where it would undergo a thermal treatment process together with other solid radwaste. Our proposed<br />
process could reduce the Eurobitum volume considerably. The most flammable and the least radiation resistant molecules and the<br />
nitrates were removed from the original Eurobitum waste. <strong>Final</strong>ly, the residual waste is expected to be more stable in geological<br />
disposal conditions.<br />
5) STANDARDIZING OF LLW/ILW TREATMENT FOR RUSSIAN<br />
TYPE PRESSURE WATER REACTORS (w/oP-59233)<br />
Klaus Buettner, Rainer Slametschka, NUKEM Technologies GmbH (Germany)<br />
According to the framework program of the Russian Federation released in 2010 it is planned to build up additional nuclear<br />
capacity of approximately 20 GWe. In addition, contracts were signed for several new-builds throughout the world. The related<br />
design efforts together with the restricted design capacities in Russia led Rosenergoatom (Client) and Atomstroyexport (Co-Client)<br />
to the set up of a so-called unified project TOI. TOImeans translated Technically Optimized reactor designed with Integrated databases.<br />
NUKEM Technologies owned by Atomstroyexport was selected to develop the standardized Technically optimized design for<br />
the treatment of the generated LLW and ILW. Special emphasis was made to reduce the waste volume for storage after treatment<br />
to below 50 m³ per year and unit. The selected treatment technologies compromise sorting, fragmentation, thermal treatment, compaction,<br />
evaporation, cementation etc.<br />
In 2010 NUKEM Technologies together with Atomenergoprojekt (Main Contractor) developed the technical concept for the<br />
treatment of liquid and solid LLW and ILW generated within the reactor as well as in the auxiliary buildings. In an iterative process<br />
the waste amounts generated and the respective treatment methods were discussed and agreed. The next step will be to further<br />
develop the design. The basic design (technical project) should be finalized until end of 2012.<br />
58
Abstracts Session 6<br />
6) 35 YEARS OF INCINERATION IN STUDSVIK, LESSONS LEARNED<br />
AND RECENT MODIFICATIONS AND IMPROVEMENTS (wP-59264)<br />
Maria Lindberg, Karin von Kronhelm, Joakim Lövstrand, Studsvik Nuclear AB (Sweden)<br />
In 1976 Studsvik, Sweden, started operation of its incinerator and has since been in operation. The incinerator facility is<br />
licensed for 600 tonnes per year and during 2010 around 500 tonnes were treated.<br />
The waste incinerated arises both in the nuclear industry, including the Studsvik site, as well as other industries where radioactivity<br />
is used such as hospitals, universities and other research activities. Waste from customers in different countries has been treated<br />
over the years, for example Swedish and German nuclear power plants, fuel vendors in Sweden, Germany and the UK as well<br />
as the Studsvik site it self.<br />
The last few years the facility waste acceptance criteria has been upgraded to also accept flame retardant plastics as well as<br />
oils, solvents and oil soaks. In order to do this the facility it self has also been upgraded.<br />
The latest new waste stream that can be accepted is activated carbon from off-gas treatment systems. This waste stream is treated<br />
by grinding the pellets before incineration. A recent test has shown that this approach works really well and that the amount of<br />
ash and dust is very small. Studsvik is currently awaiting the final authority approval for this waste stream and…<br />
7) SODIUM-RICH WASTES: CHALLENGES, ANALYSIS AND PERFORMANCE (w/oP-59316)<br />
Daniel Brew, Melody L Carter, Lou Vance, Martin W Stewart, ANSTO (Australia)<br />
The immobilisation of radioactive waste is of fundamental importance to its safe management. By changing the form of the<br />
waste, chemically and/or physically, it is possible to minimise the escape of radionuclides to the biosphere. Sodium-rich wastes can<br />
be particularly problematic to immobilise. The high solubility of sodium in both acidic and alkaline water makes it particularly challenging<br />
to maintain as a structural component within the wasteform matrix. Glass and glass-ceramic wasteforms have been developed<br />
at the Australian Nuclear Science & Technology Organisation (ANSTO) that immobilise sodium-rich wastes (up to 7 M<br />
NaOH) in accordance with US Department of Environment regulations. While traditional chemical and structural analyses such as<br />
powder infra-red spectroscopy, thermal gravimetry and x-ray diffraction have been employed in this development, additional data<br />
from neutron- and X-ray micro-focus tomography are also presented. These techniques were used to quantify phase volume percentage<br />
and size distribution data to further elucidate structural information and matrix uniformity. This work presents the ANSTO<br />
experience of sodium-rich wastes: the process involved from laboratory design with key results, to upscale considerations and challenges.<br />
8) PRELIMINARY DEMONSTRATION OF GEOMELT TREATMENT OF<br />
HANFORD’S K-BASIN SLUDGE (wP-59004)<br />
Keith Witwer, IMPACT Services, Inc. (USA)<br />
The U.S. Department of Energy (DOE) and CH2M Hill Plateau Remediation Company (CHPRC) are seeking a waste treatment<br />
solution for sludge stored in the K-Basin spent fuel pond at the Hanford Nuclear Site, in Washington State, USA. This sludge<br />
is a Remote Handled Transuranic (RHTRU) waste destined for final disposal at the Waste Isolation Pilot Pant (WIPP) in New Mexico.<br />
Removal of the sludge from the K-Basin and transport for interim storage at the Hanford Site is referred to as Phase 1 in this<br />
process. Phase 2 is defined as the treatment and packaging of the sludge such that it can be transported and disposed at the WIPP.<br />
This paper discusses work in support of Phase 2.<br />
ISIs GeoMelt ICV process is ideally suited to treating a heterogeneous sludge that is rich in uranium metal and which contains<br />
a mixture of other fuel derived products, earthen materials, and miscellaneous items (operational debris, resin, etc). GeoMelt can<br />
quickly and efficiently treat small drum load batches and will fully destroy organics, oxidize reactive metals, and permanently<br />
immobilize radioactive constituents within a high-integrity vitrified product that will meet or exceed all WIPP acceptance criteria.<br />
The GeoMelt Technology has an extensive experience base, having…<br />
SESSION 6 — ISSUES AND SOLUTIONS RELATED TO SPENT FUEL, TRU, AND<br />
HLW TRANSPORTATION AND DISPOSAL (2-5)<br />
1) INITIAL ASSESSMENT OF RADON IN A DEEP GEOLOGICAL<br />
REPOSITORY FOR USED NUCLEAR FUEL (wP-59145)<br />
Kelly Sedor, Frank Garisto, Helen Leung, Nuclear Waste Management Organization (Canada)<br />
The Nuclear Waste Management Organization is implementing Adaptive Phased Management (APM) for the long-term management<br />
of Canadas used nuclear fuel. The APM approach encompasses centralized containment and isolation of the used fuel in<br />
a Deep Geological Repository (DGR) in a suitable rock formation, such as crystalline rock or sedimentary rock.<br />
During the construction and operation of a DGR, workers will be exposed to radon in air emanating from the repository host<br />
rock. In open air, the concentration of radon gas is very small. In confined spaces, such as the DGR, radon gas has the potential to<br />
accumulate and reach relatively high concentration levels, and may become a health hazard to workers.<br />
An initial assessment of the radon hazard of the DGR concept was performed to determine whether there is a health hazard to<br />
workers, and any need for radon monitoring during construction and operation.<br />
The radon concentration in various locations was estimated based on properties of the host rock (including uranium content,<br />
porosity and saturation), radon emanation rate, ventilation rate, and dimensions of the repository. Specifically, the analysis considered:<br />
the radon concentration in the DGR during construction and operations; the radon concentration at the repository site,<br />
including that adjacent to…<br />
59
Session 6 Abstracts<br />
2) GROUNDWATER FLOW MODELING OF PERIODS WITH TEMPERATE CLIMATE CONDITIONS FOR USE IN<br />
A SAFETY ASSESSMENT OF A REPOSITORY FOR SPENT NUCLEAR FUEL (w/oP-59154)<br />
Steven Joyce, Lee Hartley, Serco; Trevor Simpson, Serco (UK)<br />
As a part of the license application for a final repository for spent nuclear fuel, the Swedish Nuclear Fuel and Waste Management<br />
Company (SKB) has prepared a safety report (SR-Site) that assesses the long-term radiological safety after closure of a repository<br />
located at 500 m depth in the Forsmark area, c. 120 km north of Stockholm. The movement and composition of groundwater<br />
affect both the key pathways for radionuclide migration and the performance of engineered barriers, and hence are important issues<br />
that have to be considered and modelled as part of quantitative assessment calculations. This presentation describes the groundwater<br />
flow modelling studies that have been performed to represent the post-closure hydrogeological and hydrochemical situations<br />
during temperate climate conditions, and how these are used to support safety assessment calculations and arguments.<br />
The collation and implementation of onsite hydrogeological and hydrogeochemical data from the surface based site investigations<br />
at Forsmark are used as the basis for defining a reference case for the natural hydrogeological situation at the site (hydrogeological<br />
base case). Areas of uncertainty within the current site understanding and the engineered system are examined by a<br />
series of flow model variants. The flow modelling needs to consider a wide range of…<br />
3) CONCEPTION OF A NEW CONDITIONING PROCESS, OF STRONGLY PLUTONIUM<br />
CONTAMINATED WASTE CANISTERS (w/oP-59205)<br />
Maxime Michel-Noel, ONET Technologies-ONECTRA (France)<br />
Intermediate storage in the Pegase nuclear facilities, of wastes strongly contaminated with plutonium and conditioned in 100<br />
litres canisters, was no longer possible due to the new safety evaluation of this installation. A new process have been then imagined<br />
to transform all these canisters in new confined packages inside the building itself. The conception, which is described, is based<br />
on safety risk analysis which has been conducted before the construction.The operation itself is now terminated.<br />
4) METHODOLOGICAL GUIDE ON DEVELOPMENT OF WORK PLAN FOR MITIGATION OF ACCIDENT<br />
CONSEQUENCES DURING TRANSPORTATION OF RADIOISOTOPE THERMOELECTRIC GENERATORS AND<br />
RADIOISOTOPE HEAT SOURCES (w/oP-59162)<br />
Valeriy Shempelev, Scientific and Engineering Centre for Nuclear and Radiation Safety; Vladimir Reka, Rostechnadzor;<br />
Malgorzata Sneve, Norwegian Radiation Protection Authority; Alexander Smetnik, Evgenij Kapralov,<br />
FSUE VO “Safety”; Galina Zubareva, Tver State Medical Academy (Russia/Norway)<br />
This methodological Guide has been built on the requirements of the regulatory acts of the Russian Federation, federal codes<br />
and standards in the field of atomic energy, and also recommendations of the IAEA regulating the issues of safety during transportation<br />
of radioactive material, and is intended to provide methodological aid to the operation organizations (operators), consignors<br />
and consignees, when planning and organization of work on mitigation of accident consequences during transportation of<br />
Radioisotope Thermoelectric Generators (RTG) and Radioisotope Heat Sources (RHS) by transport of all types, by land, air and<br />
water all over the territory of the Russian Federation.<br />
The methodological Guide contains recommendation on the procedure of preparation and execution of the Work Plan for mitigation<br />
of accident consequences and its sections, as well as a standard model of the Plan and agreement with emergency and rescue<br />
units for implementation of work to prevent transport incidents and accidents when transporting RTG and RHS drafted on the<br />
basis of results of generalizing the real plans developed by the operating organizations. RTG utilize heat energy from radioactive<br />
isotopes, in this case 90Sr and its daughter nuclide 90Y, to generate electricity as a power source.<br />
5) PHYSICAL AND CHEMICAL PROCESSES DURING VACUUM DRYING<br />
OF METALLIC SPENT NUCLEAR FUEL (wP-59114)<br />
Martin Plys, Michael Epstein, Sung Jin Lee, Robert Apthorpe, Fauske & Associates LLC (USA)<br />
A key process step in remediation of metallic spent nuclear fuel is vacuum drying, in order to move such fuel from pool storage<br />
to dry storage. The drying process for metallic spent nuclear fuel is complicated by the fact that it must accommodate failed<br />
fuel elements, scrap pieces of fuel elements, and scrap particulate. A number of physical and chemical processes that must be considered<br />
in order to effectively and safely vacuum dry these materials are discussed in this paper including: (1) Exothermic oxidation<br />
of exposed metallic surfaces, (2) The impact of uranium hydrides that may be present, (3) The potential for thermal instability,<br />
(4) Degradation of thermal conductivity at low pressures, (5) Multi-component diffusion in scrap and particulate, and (6) Behavior<br />
of uranium oxide hydrates.<br />
We have addressed these issues by creating models for the individual phenomena that are based upon experimental data, integrating<br />
these models into the process simulation code, FATE, and validating process simulations against closed-form solutions. The<br />
integrated model has been employed during the conceptual and preliminary design phases for vacuum drying of scrap particulate<br />
at Hanford in order to converge upon design and operational features that are demonstrably robust and therefore minimize safetyrelated<br />
technical specifications<br />
6) SECURITY ISSUES FOR LONG-TERM STORAGE OF USED FUEL (w/oP-59380)<br />
Felicia A Durán, Gregory Wyss, Calvin Jaeger, Sandia National Laboratories (USA)<br />
With the uncertain future of the proposed Yucca Mountain Repository for final disposal of used light water reactor fuel, the<br />
need to store these fuels past their current regulatory certification periods has become clear. This situation presents possible regulatory<br />
and technical issues with regard to both storage safety and security. The U.S Department of Energy (DOE), Office of Nuclear<br />
Energy (NE) is engaged in a program to develop the technical bases for extending dry storage and subsequent transportation of used<br />
nuclear fuel (UNF). The DOE/NE program addressing this issue is divided into four main topical areas: Research and Development<br />
(R&D) Opportunities, Security, Transportation, and Concept Evaluations. This paper will discuss work to address security<br />
issues for long-term storage of UNF. The timeframe for long-term management of UNF is currently defined to be on the order of<br />
60
Abstracts Session 7<br />
300 years. This longer timeframe presents possible regulatory and technical issues with regard to both storage safety and security.<br />
Issues associated with maintaining security for very long-term storage are being identified and addressed. An assessment has been<br />
performed of security regulations, including those from the U.S. Nuclear Regulatory Commission and the DOE, for impacts over<br />
the longer timeframe. The characterization of UNF as self-protecting...<br />
SESSION 7 — NATIONAL AND INTERNATIONAL ER PROGRAMS (4.2)<br />
1) OBJECTIVES FOR REMEDIATION OF AREAS POLLUTED BY<br />
RADIOACTIVE SUBSTANCES IN FRANCE (w/oP-59300)<br />
Charlotte Cazala, Didier Gay, Olivier Chabanis, Jerome Guillevic, IRSN; Odile Palut Laurent,<br />
Geraldine Dandrieux, ASN; Alain Thomassin, IRSN/DRPH/SER/UETP; Chapalain Estelle,<br />
Laurence Roy, Ministère de lEcologie, du Développement Durable, des Transports et du Logement (France)<br />
In the 90s, the French administration has developed several tools in order to inventory potentially polluted sites and to identify<br />
those requiring an immediate action. Concerns and needs have gradually moved on and a methodology for the management of<br />
selected areas was established. A general framework was then published by the Ministry of Ecology in 2007.<br />
The Ministry of Ecology jointly with the Nuclear Safety Authority (ASN) asked the Institute for Radiological Protection and<br />
Nuclear Safety (IRSN) to establish guidelines for the management of radioactive polluted areas . Requirements were: i) to fit with<br />
the published general framework while highlighting specificities of radioactive pollutants management; ii) to take benefit of<br />
radioactive polluted areas remediation; iii) to precise remediation objectives and iv) to develop stakeholders involvement issues.<br />
Within this general framework, two situations were identified: i) the polluted area is already used for domestic, public or industrial<br />
purposes; ii) the polluted area is an industrial site under dismantling or a polluted wasteland where a redevelopment project is<br />
under consideration.<br />
Management of a polluted site with ongoing use is based on the pollution level determination. This level can be compared to<br />
threshold values defined in applicable regulations when such threshold values do…<br />
2) REMEDIATION OF AREVA MIRAMAS SITE (w/oP-59312)<br />
Gilles Potier, AREVA (France)<br />
Remediation of AREVA Miramas site<br />
Objectives : The objectives of this project is to remediate the former facility by performing all operations useful and necessary<br />
enabling a final withdrawal of CEA and AREVA NC companies. The desired end state is a remediated site for a new industrial use<br />
Environmental Context : The various studies have demonstrated and confirmed the presence of soil contaminations. The types<br />
and ranges of pollution could clearly be attributed to different historical activities : metals; mercury and organic compounds. However,<br />
due to the different constraints (Mercury regulation, urban proximity, slick ...) and to a particular sensitivity (AREVA operator,<br />
site located in a urban area), the project cannot be limited to the strict regulatory requirements<br />
Description of operations : The operations concerns the remediation of approximately 100 000 m3 of soil and the decommissioning<br />
of facilities. Soil remediation focuses on two major pollutants: mercury and organo-nitro compounds, located in areas well<br />
identified. The techniques applied will be...<br />
3) THE VALUE OF A MATURE, STABLE, AND TRANSPARENT REGULATORY FRAMEWORK<br />
IN FACILITATING ER PROGRAMS LESSONS LEARNED IN DECOMMISSIONING OF<br />
URANIUM RECOVERY AND OTHER FACILITIES IN THE USA (w/oP-59411)<br />
Keith I. McConnell, Larry Camper, U.S. Nuclear Regulatory Commission (USA)<br />
The history of decommissioning activities in the United States has demonstrated the value of a mature, stable and transparent<br />
regulatory framework in facilitating the timely completion of environmental remediation. Two examples are given as case studies.<br />
The first example relates to the history of uranium concentrate (yellowcake) production in the U.S. to support the initial development<br />
of civilian nuclear power in the U.S. in the 1950s, 60s, 70s and 80s. This yellowcake production, which took place mostly in<br />
the western U.S., was undertaken before laws and regulations to prevent contamination and protect public health and safety were<br />
fully developed. Significant contamination occurred in terms of both surface and ground water contamination. Although most conventional<br />
mills producing uranium during these early years entered decommissioning in the 70s and 80s, the vast majority are still<br />
remediating their sites because of persistent contamination in ground water. Had an effective regulatory framework been in place,<br />
much of this contamination would have been prevented and remediation accomplished more effectively. In contrast to this experience,<br />
a second example is provided related to development of the regulatory framework for decommissioning of non-uranium<br />
recovery facilities in the U.S. in the late 1990s and early 2000s. Prior to this...<br />
4) THE FIRST NEW CONVENTIONAL URANIUM MILL IN THE U.S. IN 30 YEARS LICENSING<br />
OF THE PINON RIDGE PROJECT, COLORADO, USA (w/oP-59330)<br />
Steve Brown, SENES Consultants Ltd; Frank Filas, Energy Fuels Resources, Lakewood, (USA)<br />
Energy Fuels Resources Corporation (EFR) has recently received a radioactive material license from the US State of Colorado<br />
and intends to construct and operate a conventional acid leach uranium and vanadium mill at the Piñon Ridge Mill site in western<br />
Montrose County, Colorado. Site facilities will include an administration building, a 17- acre mill; three tailing cells totaling 90<br />
acres, a 40-acre evaporation pond (expandable capacity to 80 acres), a 6-acre ore storage pad, and an access road. The mill will<br />
process ore produced from mines within a reasonable truck-hauling distance, mostly from the historical Uravan mineral belt of the<br />
Colorado Plateau (Four Corners region of the States of Utah, Colorado, Arizona and New Mexico) and will have a capacity of 500<br />
tons per day, but is designed to accommodate subsequent expanded production capacity of up to 1,000 tons per day. The expected<br />
operating life of the mill is 20 to 40 years, depending on the production rate.<br />
The Piñon Ridge mill is subject to regulation by the state of Colorado as a Agreement State with the U.S. Nuclear regulatory<br />
Commision under the U.S. Atomic Energy Act. Accordingly, the mill license (radioactive source material license) that was issued<br />
in January…<br />
61
Session 7 Abstracts<br />
5) INTEGRATED PROGRAM MANAGEMENT FOR MAJOR NUCLEAR DECOMMISSIONING<br />
AND ENVIRONMENTAL REMEDIATION PROJECTS (w/oP-59068)<br />
John Lehew, CH2M Hill Plateau Remediation Company (USA)<br />
CH2M HILL Plateau Remediation Company (CH2M HILL) is the U.S. Department of Energys (DOE) contractor responsible<br />
for the safe, environmental cleanup of the Hanford Sites Central Plateau, sections of the Columbia River Corridor and the Hanford<br />
Reach National Monument.<br />
The 586-square-mile Hanford Site is located along the Columbia River in southeastern Washington, U.S.A. A plutonium production<br />
complex, housing the largest volume of radioactive and contaminated waste in the nation, with nine nuclear reactors and<br />
associated processing facilities, Hanford played a pivotal role in the nation’s defense for more than 40 years, beginning in the 1940s<br />
with the Manhattan Project. Today, under the direction of the DOE, Hanford is engaged in one of the world’s largest environmental<br />
cleanup project.<br />
The Plateau Remediation Contract is a 10-year project paving the way for closure of the Hanford Site. The site through its location,<br />
climate, geology and proximity to the Columbia River in combination with the results of past nuclear operations presents a<br />
highly complex environmental remediation challenge. The complexity is not only due to the technical issues associated with<br />
decommissioning nuclear facilities, remediating soil contamination sites, dispositioning legacy waste and fuel materials and integrating<br />
these with the deep vadose zone and groundwater remediation,…<br />
6) EPRI NUCLEAR POWER PLANT GROUNDWATER PROTECTION PROGRAM (w/oP-59341)<br />
Karen Kim, Electric Power Research Institute (USA) - Presentation by Sean Bushart, EPRI (USA)<br />
The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The<br />
Nuclear Power Plant Groundwater Protection <strong>Program</strong> conducts research related to the management of groundwater at nuclear<br />
power plant sites.<br />
Experiences at decommissioned and operating nuclear power plants show that leaks and spills from plant systems, structures,<br />
and components and work practices can lead to contamination on on-site soils and groundwater. While the levels of radioactivity<br />
resulting from such contamination events do not pose health and safety threats to the public, they have raised stakeholder concerns<br />
and, in some cases, have required remediation during decommissioning to meet site-release criteria. The EPRI Nuclear Power Plant<br />
Groundwater Protection <strong>Program</strong> provides technical support and guidance to the industry for prevention of leaks and spills, early<br />
detection of leaks and spills, monitoring of groundwater contamination, prevention of off-site migration of groundwater contamination,<br />
and remediation of groundwater and soil contamination. The EPRI Groundwater Protection <strong>Program</strong> is composed of two<br />
main objectives: 1) provide technical guidance and 2) develop advanced technologies.<br />
The cornerstones of the EPRI Groundwater Protection <strong>Program</strong> are the EPRI Groundwater Protection Guidelines for Nuclear<br />
Power Plants and the EPRI Groundwater and Soil Remediation Guidelines. These Guidelines documents<br />
7) CLEAN UP STRATEGIES AND RESULTS IN USIN SITE IN SÃO PAULO CITY, BRAZIL (w/oP-59243)<br />
Rodrigo Raposo de Almeida, Federal Fluminense University;<br />
Valter J.G. Mortágua, Industrias Nucleares do Brasil (Brazil)<br />
This paper presents the experience of the team of technicians and consultants from INB (Industrias Nucleares do Brazil SA)<br />
in activities related to environmental remediation of soils contaminated by radionuclides of natural series of uranium and thorium<br />
in the USIN unit (old mill Interlagos).<br />
In 2007 was elaborated a master plan for remediation the USIN site, after 6 months the plan was approved by CNEN, the<br />
nuclear regulatory agency in Brazil. Given the lack of a final deposit of radioactive residues in Brazil, the elaborate plan aimed to<br />
minimize the volume of radioactive waste final. A criterion was developed to fractionate the tailings at three levels. The waste level<br />
1, with activity of 226Ra and 228Ra below 0.5 Bq/g and the effective dose of less than 1.0 mSv/yr, may remain in the area. The<br />
waste level 2, with activity of 226Ra and 228Ra than 0.5 Bq/g and individual effective dose exceeding 1,0 mSv/yr, but with total<br />
activity below 30 Bq/g may be disposed in municipal landfills. The waste level 3, with total activity above 30 Bq/g should be stored<br />
in steel drums of 200 liters and stored in a radioactive residues warehouse.<br />
Considering that the time for radiometric analysis is…<br />
8) APPLICATION OF AN ENVIRONMENTAL REMEDIATION METHODOLOGY:<br />
THEORY VS. PRACTICE. REFLECTIONS AND TWO BELGIAN CASE STUDIES (wP-59184)<br />
Koen Mannaerts, Stephane Pepin, Boris Dehandschutter,<br />
Walter Blommaert, Federal Agency for Nuclear Control (FANC) (Belgium)<br />
Like in many countries, polluted industrial sites also exist in Belgium. Although the contamination is purely chemical in most<br />
cases, they may also contain a radioactive component. For chemically contaminated sites, extensive regulations and methodologies<br />
were already developed and applied by the different regional authorities. However and essentially because radioactivity is a federal<br />
competence, there was also a necessity for developing a legal federal framework (including an ER-methodology) for remediation<br />
of radioactive contaminated sites. Most of the so-called radioactive contaminated sites are exhibiting a mixed contamination<br />
(chemical and radiological), and hence the development of such methodology had to be in line with the existing (regional) ones<br />
concerning chemical contamination. Each authority having their own responsibilities with regard to the type of contamination, this<br />
makes it more complicated and time-consuming finding the best solution satisfying all involved parties. To overcome these difficulties<br />
the legal framework and methodology - including the necessary involvement of the stakeholders and delineation of each partys<br />
responsibilities - has to be transparent, clear and unambiguous.<br />
Once the methodology is developed as such and approved, the application of it is expected to be more or less easy, logic and<br />
straightforward. But is this really true? The aim this…<br />
62
Abstracts Session 8<br />
SESSION 8 — EXPERIENCES IN ER CLEAN-UP METHODS AND ACTIONS (4.4)<br />
1) GROUNDWATER REMEDIATION OF HEXAVALENT CHROMIUM ALONG THE<br />
COLUMBIA RIVER AT THE HANFORD SITE IN WASHINGTON STATE, USA (wP-59030)<br />
Dyan Foss, CH2M Hill Plateau Remediation Company; Briant Charboneau, DOE RL (USA)<br />
The U.S. Department of Energy Hanford Site, formerly used for nuclear weapons production, encompasses 1500 square kilometers<br />
in southeast Washington State along the Columbia River. A principle threat to the river are the groundwater plumes of hexavalent<br />
chromium (Cr(VI)), which affect approximately 9.8 square kilometers, and 4.1 kilometers of shoreline.<br />
Cleanup goals are to stop Cr(VI) from entering the river by the end of 2012 and remediate the groundwater plumes to the drinking<br />
water standards by the end of 2020. Five groundwater pump-and-treat systems are currently in operation for the remediation of<br />
Cr(VI).<br />
Since the 1990s, over 13.6 billion liters of groundwater have been treated; over 1,435 kg of Cr(VI) have been removed. This<br />
paper describes the unique aspects of the site, its environmental setting, hydrogeology, groundwater-river interface, riverine<br />
hydraulic effects, remediation activities completed to date, a summary of the current and proposed pump-and-treat operations, the<br />
in situ redox manipulation barrier, and the effectiveness of passive barriers, resins, and treatability testing results of calcium polysulfide,<br />
biostimulation, and electrocoagulation, currently under evaluation.<br />
2) ENVIRONMENTAL REMEDIATION OF AN ALSTOM GRID INDUSTRIAL SITE (FRANCE) (wP-59270)<br />
Stéphanie Romero, ALSTOM GRID (France)<br />
ALSTOM Grid is the project owner of the remediation of a former industrial site, located in Saint-Ouen, north of Paris. The<br />
industrial activity (power transformer production) started in 1921 and stopped in 2006. The type of pollution is linked with the former<br />
activity. It’s an organic pollution: hydrocarbon, PCB and chlorinated volatile organic compounds. The clean-up concerns soil<br />
and groundwater.<br />
The main specificity of the project is that the remediation is operated inside the existing industrial buildings which must be<br />
kept in place and restituted to the owner after the works. The treatment of soil requires excavating soil up to 9 m deep (1 m under<br />
the level of the groundwater) inside the buildings. As a consequence, some impressive devices were set up to ensure the stability<br />
of the buildings during the clean-up, like support structures of the foundations and strengthening of the building fronts.<br />
In the same time, it has to be pointed out that great diversity of clean-up actions is performed on the site: the soil is excavated<br />
to be treated on site (bioremediation or chemical treatment) or off site. The treatment of groundwater consists of pumping the oil<br />
staying on the surface and oxidizing the dissolved pollution.<br />
This project is probably the first experience of this scale in France with multi-contaminated soil and groundwater decontamination<br />
in keeping and reinforcing the existing buildings.<br />
3) DESIGN AND INSTALLATION OF A PERMEABLE TREATMENT WALL TO PASSIVELY<br />
REMOVE STRONTIUM-90 FROM GROUNDWATER AT A FORMER COMMERCIAL<br />
NUCLEAR FUEL REPROCESSING FACILITY IN NEW YORK (wP-59292)<br />
Douglas Bablitch, Rupeet Malhotra, Richard Frappa, Scott Warner, AMEC Geomatrix (USA)<br />
A permeable treatment wall (PTW) was designed and installed at the West Valley Development Project (WVDP), a former<br />
commercial nuclear fuel reprocessing facility in New York, to passively remove and contain the expansion of strontium-90 (Sr-90)<br />
in the site groundwater. AMEC engineers and geologists have collaborated with researchers at the State University of New York at<br />
Buffalo (UB) and West Valley Environmental Services LLC to design and install an approximately 260 meter (860-foot) long by<br />
0.9 meter (3-foot) thick zone of granular zeolite (a natural aggregate composed of approximately 85 percent of the mineral clinoptilolite)<br />
that will remove Sr-90 in situ from groundwater through ion-exchange reactions. The PTW was designed to meet the functional<br />
objectives for up to 20 years; performance monitoring will be conducted regularly and will be used to assess the lifetime efficacy<br />
of the PTW. The zeolite-filled PTW was the selected remedial alternative due to its hydraulically passive operations and lower<br />
life-cycle cost over other more traditional active treatment alternatives such as pump and treat.<br />
The design relied heavily on detailed site characterization of site soils and groundwater conditions and bench and pilot scale<br />
evaluations of various zeolite materials. The design specified the use of a one-pass…<br />
4) DECOMMISSIONING OF THE ACTIVE STORAGE FACILITY FOR RESIDUALS IN RHEINSBERG<br />
(BRANDENBURG/GERMANY) AND RESULTS OF GROUNDWATER MONITORING (wP-59134)<br />
Mathias Steinhoff, Öko-Institut e.V. (Germany)<br />
The Active Storage Facility for Residuals (Aktives Lager für Rückstände ALfR) an open air controlled area has been used<br />
for storage of radioactive waste (liquid and solide waste) at the site of the NPP Rheinsberg in the former GDR. Liquid waste has<br />
been cemented and dumped for near surface final disposal.<br />
During period of operation of ALfR some incidents happened. Residues of evapo-rated cooling water of unknown amount (ca.<br />
1-10 m³), the drop out from small leak-ages and wash off from contaminated open air storage barrels contaminated the soil.<br />
Since 1997 the buildings of the ALfR are decommissioned and the site will be reme-diated. From the beginning of decommissioning<br />
up to now the groundwater has been monitored.<br />
This paper shows different steps of decommissioning and explains the experience of groundwater monitoring. Currently 33<br />
sampling points are used for sampling groundwater of different layers. The radiological parameters under examination are Cobalt-<br />
60, Cesium-137, Strontium-90 and Tritium. Non radiological Parameters like Bore, Potassium, Sodium, Nitrate, pH value and TOC<br />
(total organic carbon) are also investigated.<br />
Since 1997 activity concentration of Cobalt-60 and Tritium in groundwater has de-creased. The activity concentration of Strontium-90<br />
had increased from 1997 to 2007. Since 2007<br />
63
Session 9 Abstracts<br />
5) ENVIRONMENTAL SURVEILLANCE SYSTEM FOR THE SHCHUCHYE SITE (wP-59042)<br />
Stephane Belbeze, Matthieu Hallouin, Antea (France)<br />
An intergovernmental agreement on cooperation about chemical weapon destruction was signed between France and the Russian<br />
federation on 14th February 2006 in the context of a Global Partnership dedicated to preventing catastrophic terrorism and the<br />
proliferation of weapons of mass destruction. It came into effect on 25th April 2007 after ratification by both countries. The present<br />
demonstrated project was launched as part of this collaboration on the Shchuchye site (Russia – Kurgan Oblast). The project<br />
concerned the environmental surveillance system for the Shchuchye site required for the safe operation of the installation used to<br />
destroy chemical weapons.<br />
The aim was to implement equipments and methods of analysis for very low concentrations of pollutants in the three environmental<br />
compartments: air, water and soil. This has been achieved with the help of industry and other organizations in France (Environment/SA<br />
for supplies, INERIS and Antea Group) and Russia (ROST Association and EKROS Engineering). This system takes<br />
account of the normal operation of the installation as well as incident management. It includes 11 stationary atmospheric measuring<br />
stations constructed by Environment/SA and EKROS Engineering including ASTEK dedicated toxic gas detector : “Terminator<br />
FOV-1”, 3 mobile atmospheric measuring stations, 2 mobile soil & water measuring stations, 4 sampling cars constructed by<br />
Environment/SA and EKROS Engineering, a complete Chemical analysis laboratory which can handle ppb analysis of toxic gases,<br />
organics and minerals pollutants, an information collection center and a meteo station which can retrieve, display and archive all<br />
the datas or alarm from the stationary and mobile stations. Antea Group has provided a technical expertise and various negotiations<br />
during the negotiation phase, the project initiation files & contracts redaction, the project Monitoring and reporting to stakeholders,<br />
the REX. Up to 2009, No other site of the world uses such an innovative system. Antea Group worked on this project for 4<br />
years. It successfully began operating in March 2009, before the start of destruction operations, after 15 months of work on the site.<br />
6) 25 YEARS AFTER CHERNOBYL NPP ACCIDENT: EXPERIENCE AND TRENDS OF RADIOACTIVE<br />
CONTAMINATED SOILS REHABILITATION IN BELARUS (wP-59242)<br />
Leanid Maskalchuk, JIPNR-Sosny NAS of Belarus (Belarus)<br />
The paper describes the developed and applied soil decontamination measures and methods in Belarus after the Chernobyl<br />
NPP accident. It is considered the possibility of using of organomineral amendments based on natural raw materials (sapropel)<br />
and industrial wastes (hydrolyzed lignin, clay-salt slimes) for rehabilitation of radioactive contaminated soils.<br />
SESSION 9 — POSTER SESSION: LOW/INTERMEDIATE LEVEL WASTE MANAGEMENT (1.1)<br />
1) NUMERICAL MODELING FOR COLLOID-FACILITATED MIGRATION OF N-NUMBER<br />
RADIONUCLIDES CHAINS IN THE FRACTURED ROCK (w/oP-59257)<br />
Chun-Ping Jen, National Chung Cheng University (Taiwan)<br />
A previous numerical model for N-member radionuclide decay chains has been extended to include the effect of radionuclide<br />
sorption with groundwater colloids. Published distribution coefficients were employed in the nuclide decay chain to illustration the<br />
present model. The colloid concentration was assumed constant in time and space owing to equilibrium between colloid generation<br />
and sedimentation by chemical and/or physical perturbations. Furthermore, the diffusion of colloids into the rock matrix was<br />
ignored because the diameter of colloid is relatively large and colloids and fracture surfaces are like-charged. The results indicated<br />
that colloids could facilitate the transport of radionuclides and the large adsorbability of nuclides with colloids enlarged the effect<br />
of acceleration by colloids. The influence of colloids on the radionuclide transport was expected to be crucial to the actinides with<br />
large adsorbability; however, the present results revealed that the low-adsorbing nuclides whose parent nuclides have large capability<br />
of sorption could be also facilitated significantly by colloids indirectly. Therefore, the role of colloids played in the transport<br />
of the radionuclides decay chain should be assessed carefully in the radioactive waste disposal. The numerical method presented<br />
herein is helpful to verify/validate further complex far-field models.<br />
2) LABORATORY EXPERIMENTS ON THE ALTERATION OF HIGHLY-COMPACTED BENTONITE BY<br />
ALKALINE SOLUTION AND THE EFFECTS ON PHYSICAL PROPERTIES (wP-59318)<br />
Satoru Miyoshi, Shinya Morikami, Yukinobu Kimura, Tomoko Jinno, Shuichi Yamamoto, Obayashi Corporation (Japan)<br />
The issue has to be considered for the evaluation of performance of multiple burrier systems in geological repository of<br />
radioactive waste wheather alkaline leachate from cement matterials may alterate clay materials so that they can not show the<br />
required performance. In order to study on the alkali alteration of compacted bentonite and the effect on the physical properties,<br />
using modified consolidation apparatus, we have done a series of experiments for a long term such that alkali solution is injected<br />
into compacted bentonite to measure the temporal change of swelling pressure, flow rate, and the compositions of outflow solution.<br />
We settled two cases for the experiment: one is the case where 1.0 mol/L sodium hydroxide solution is injected (case 1) and<br />
the other saturated calcium hydroxide solution (case 2). The dry density of specimen for both cases are 1.6 g/cm3. The dissolution<br />
of the minerals in the high-pH environment is mainly considered in case 1 and the effect of the secondary minerals to be generated<br />
in calcium rich environment is mainly considered in case 2. The experiment is done in the bath with constant temperature 70<br />
celcius degree to reasonably accelerate the reaction of alkali alteration. In addition to the above measurements, a series of analysis<br />
of solid phase is done after one and half year injection of alkaline solution. Through the experiment, we found that the dissolution<br />
rate of montmorillonite is much lower than those of accompanying minerals and that the physical properties are reasonably kept<br />
even though some part of the minerals are dissolved.<br />
64
Abstracts Session 9<br />
3) GAS TRANSPORT PROPERTIES OF PUMICE TUFF FOR PERFORMANCE<br />
ASSESSMENT OF LLW DISPOSAL FACILITY (wP-59074)<br />
Shuichi Yamamoto, Kenichiro Suzuki, Obayashi Corporation; Mamoru Kumagai, Japan Nuclear Fuel Limited;<br />
Yasuhiro Tawara, Koji Mori, Geosphere Environmental Technology Corporation (Japan)<br />
In Japan, some of the radioactive waste with a relatively higher radioactivity concentration from nuclear facilities is to be packaged<br />
in rectangle steel containers and disposed of in sub-surface disposal facilities, where normal human intrusion is unlikely to<br />
occur. If dissolved oxygen in pore water is consumed by steel corrosion after the closure of the facility, hydrogen gas will be generated<br />
from the metallic waste, steel containers and concrete reinforcing bars largely by anaerobic corrosion. If the generated gas<br />
accumulates and the gas pressure increases excessively in the facility, the facilitys barrier performance might be degraded by<br />
mechanical influences such as fracturing of surrounding rock and cementitious materials or plastic deformation of the bentonite<br />
buffer.<br />
In this study laboratory experiments for gas and water transport properties of the rock were performed to evaluate gas flow<br />
through the rock mass (pumice tuff) around a facility for low level waste disposal. Based on the experimental results two-phase<br />
flow properties were evaluated by means of an inverse analysis method.<br />
The pumice tuff was subjected to hydraulic conductivity tests, water retention (moisture characteristic) tests, and gas injection<br />
tests. Non-linear properties such as relative permeability and water retention curve and hydraulic conductivity as a function…<br />
4) EXTRACTION AND CONFINEMENT OF CAESIUM USING FUNCTIONALIZED<br />
POROUS MATERIALS (w/oP-59106)<br />
Carole Delchet, Guillaume Toquer, Agnès Grandjean, Institut de Chimie Séparative de Marcoule;<br />
Joulia Larionova, Yannick GUARI (France)<br />
An original approach to immobilize caesium species that uses hybrid functionalized porous media is presented. This study is<br />
part of radioactive waste water treatment Indeed, one of the most abundant fission product to be extracted from radioactive effluents<br />
are the caesium isotopes : 137Cs (T1/2 ~30y) and 135Cs (T1/2~2.106y). Transition metal hexacyanoferrates HFC (II) or (III)<br />
exhibit better sorption properties compared to organic resins or zeolites. There are then widely studied for this application over a<br />
wide pH range and wide range of ionic strength. Moreover, they show a good resistance to ionising radiation. First we present kinetic<br />
and thermodynamic data of Cs sorption properties in batch experiment for pure K2Ni(FeCN) 6 , Co3 (Fe(CN) 6 ) 2 and<br />
Ni3 (Fe(CN) 6 ) 2 . A comparison of the kinetics parameters and adsorption capacity between these HFC is then done. Furthermore,<br />
first tests of grafting Ni3 (Fe(CN) 6 ) 2 on porous glass and ordered porous silica have allowed the extraction of Cs from an aqueous<br />
solution. Then we show that an ammoniac atmosphere during two days at ambient temperature allows closing the porosity of<br />
ordered porous silica. So this soft treatment will be tested with silica solids containing HFC and extracted caesium in order to immobilized<br />
caesium species without high temperature steps, avoiding then any volatilisation.<br />
5) PHOTOCATALYTIC AND PHOTOCHEMISTRY DEGRADATION OF LIQUID<br />
WASTE CONTAINING EDTA (wP-59144)<br />
Célia Lepeytre, Cyril Lavaud, Guillaume Serve, CEA Marcoule (France)<br />
The decontamination factor of liquid waste containing 60Co is generally weak. This is due to the presence of complexant molecules.<br />
For instance, complexation of EDTA with 60Co decreases efficiency of radioactive waste treatment. The aim of this study<br />
was to degrade EDTA in H2O and CO2 and to concentrate free 60Co in order to increase decontamination factor. A first test of<br />
radioactive waste treatment by photocatalysis was allowed to increase decontamination factor ( 60Co) from 16 to 196 with a device<br />
requiring to be improved. The present work concerns the first step of the degradation process development with a more powerful<br />
device. These first experiments were leaded to follow the only EDTA oxidation. EDTA degradation was carried out by the following<br />
Advanced Oxidation Processes (AOP): UV/H2O2 (photochemistry); UV/TiO2 (photocatalysis); UV/TiO2 /H2O2 . A specific reactor<br />
was achieved for this study. The wavelength used was 254 nm (UV-C). The photocatalytic degradation of EDTA was carried<br />
out with Degussa P-25 titanium dioxide (TiO2 ), which is a semiconductor photocatalyst. The degradation degree of EDTA and the<br />
intermediate products were monitored by TOC and ionic chromatography methods. The effects of various parameters such as pH<br />
and the quantity of H2O2 were studied. This allows us to conclude…<br />
6) HISTORICAL WASTE – BIOLOGICAL SHIELD & DOCUMENTATION DURING<br />
DECOMMISSIONING (w/oP-59056)<br />
Thomas Nellemann, Anne Sørensen, Danish Decommissioning (Denmark)<br />
Inventory records of isotopes in radioactive waste are important as documentation with respect to governmental control, final<br />
disposal and public transparency. We present a simple, practical and cost-effective method for characterization of a part of the<br />
radioactive waste from decommissioning of a research reactor: The biological shielding. The method uses documentation from the<br />
decommissioning and from the construction drawings and blueprints of the reactor as well as measurements based on samples from<br />
the facility.<br />
The data presented is from a 5MW experimental light water nuclear reactor (DR-2) shutdown in 1975 and decommissioned in<br />
2008. The method incorporates an activity distribution in the biological shield. The distribution is based on measurements of samples<br />
from across the shielding and coupled with the distance to the center of the reactor core. The exact origin of each waste item<br />
is determined from pictures from the decommissioning and from old blueprints and construction drawings of the reactor.<br />
The uncertainty and usefulness of the method is related directly to different factors such as: The amount of samples obtained<br />
and the position of these with respect to the origin of the waste, the accuracy of the documentation of the decommissioning, the<br />
size of the waste items in…<br />
65
Session 9 Abstracts<br />
7) A NUMERICAL INTERPRETATION OF DENSITY HOMOGENIZATION<br />
OF BENTONITE MATERIAL IN WETTING PROCESS (wP-59153)<br />
Atsushi Iizuka, Yusuke Takayama, Katsuyuki Kawai, Kobe University; Shinya Tachibana, Saitama University;<br />
Shintaro Ohno, Ichizo Kobayashi, Kajima Corporation (Japan)<br />
The bentonite material is expected to be a buffer in the nuclear waste disposal, since it has low permeability and excellent<br />
expansion characteristics. Its expansion characteristics through wetting process can be interpreted based on the full saturation line<br />
that is depicted as a unique line on the density and the confining pressure relationship (Kobayashi et. al., 2007). And its elasto-plastic<br />
constitutive relation can be formulated by introducing additional irreversible strain component describing the expansion of<br />
montmorillonite contained in the bentonite material. Its constitutive model can express the mechanical behavior of compacted bentonite<br />
material consistently in the unsaturated sate up to fully saturated state. Then, this paper describes the density homogenization<br />
process through a series of soil-water coupled elasto-plastic finite element simulations. Namely, we consider the cases that the<br />
bentonite composed of two specimens having different initial densities is permeated with the constant water head. Stresses and<br />
strains developing in the bentonite, particularly the density change of bentonite, are examined. According to a series of numerical<br />
simulations, the density of bentonite composed of two specimens having different initial densities is not homogenized into a certain<br />
unique value of density when the bentonite reaches fully saturated state. To confirm the simulation results, we carried out a<br />
series of experiments. The experiment results also support our simulation results.<br />
8) COMPARISON OF ORGANIC AND INORGANIC ION EXCHANGERS FOR THE TREATMENT OF<br />
RADIOACTIVE LIQUID WASTES BY ION EXCHANGE PROCESSES (w/oP-59107)<br />
Yves Barre, CEA (France)<br />
There are number of liquid processes and wastes streams at nuclear facilities that require treatment for process chemistry control<br />
reasons and/or the removal of radioactive contaminants. One of the most common treatment methods for such aqueous streams<br />
is the use of ion exchange, which is a well developed technique that has been employed for many years in the nuclear industries.<br />
Nuclear power plant process water systems have typically used organic ion exchange resins to control system chemistry to minimize<br />
corrosion and to remove radioactive contaminant. In the past decade, inorganic ion exchange materials have emerged as an<br />
increasingly important replacement or complement for conventional organic ion exchange resins, particularly in liquid radioactive<br />
waste treatment and spent fuel reprocessing applications. Inorganic ion exchangers often have the advantage of a much greater<br />
selectivity than organic resins for certain important radionuclides such as 137Cs and 90Sr. These inorganic materials have also<br />
advantages with respect to immobilization and final disposal when compared with organic ion exchangers.<br />
Fixed bed column experiments were carried out with porous titanium dioxide beads and with standard polystyrene divinylbenzene<br />
resin in order to estimate the dynamics of 90Sr decontamination from a simulated liquid wastes. We present a comparison of<br />
the kinetic and thermodynamics sorption properties between organic and inorganic ion exchangers.<br />
9) DETRITIATION OF JET PLASMA FACING COMPONENTS (w/oP-59345)<br />
Pierre Trabuc, Karine Liger, Nicolas Ghirelli, Christophe Perrais, CEA (France)<br />
Beryllium tiles are proposed for ITER and the ITER-like JET wall project. The development of detritiation / recycling methods<br />
for bulk Be and the definition of a strategy, is necessary to reduce the final waste and the constraints linked to the management<br />
of mixed Be waste.<br />
The tritium content in Be is the results of contribution of different mechanisms (activation, trapping in defects due to neutron<br />
flux, and diffusion in the bulk). In fusion machines, it is foreseen to remove a part of this tritium first with in-situ detritiation techniques,<br />
but also with ex-vessel detritiation methods. Among these methods, thermal desorption is a good candidate.<br />
In this paper, the efficiency of thermal desorption of trapped tritium using different carrier gases is assessed. Effect of oxidant<br />
and reductive gases on detritation of flakes (~20 GBq/g), limiter (~103Bq/g) and divertor (~104Bq/g) tiles, at relatively high temperature<br />
(800°C), is experimentally analysed. Best results were obtained under N2 +20%O2 , after 10 h at 800°C (during 2 days) and<br />
5 hours at 1050°C (during one day). With this treatment, it is possible to conclude that flakes, limiter and divertor tiles are allowed<br />
as Low Level Waste (between 0.4 Bq/g and 12 kBq/g).<br />
10) EXPERIMENTAL DROP TESTING OF WASTE CONTAINERS FOR THE KONRAD REPOSITORY (w/oP-59269)<br />
Tino Neumeyer, Karsten Müller, Holger Voelzke, Federal Institute for Materials Research and Testing (BAM) (Germany)<br />
The Konrad repository for not heat generating radioactive wastes was licensed in 2002 primarily. Due to legal actions the final<br />
confirmation of this license took place not until 2007. Subsequently, the Federal Office for Radiation Protection (BfS) began scheduling<br />
backfitting of the former iron ore mine into a repository. The licensed repository volume is 303,000 m3 considering estimations<br />
of expected waste volumes to be disposed off. The mine itself would offer a much larger volume. Waste packages can be disposed<br />
off as recently as the repository is ready for operation what is expected not before the end of this decade. Nevertheless, there<br />
is high interest of qualified and certified waste conditioning and packaging for disposal today, what for from BAM and BfS tested,<br />
evaluated and certified containers are needed.<br />
In recent years numerous container prototypes made of steel, concrete and ductile cast iron have been tested by BAM, the Federal<br />
Institute for Materials Research and Testing in Germany. To cover the Konrad test requirements in a conservative manner container<br />
drop tests are performed mostly onto the unyielding IAEA target of BAMs large drop test facility instead of a representative<br />
foundation of the repository.<br />
This conference contribution focuses on experimental drop…<br />
66
Abstracts Session 9<br />
11) INSTRUMENTED MEASUREMENTS ON RADIOACTIVE WASTE DISPOSAL<br />
CONTAINERS DURING EXPERIMENTAL DROP TESTING (wP-59142)<br />
Thomas Quercetti, Andre Musolff, Karsten Müller,<br />
BAM - Federal Institute for Materials Research and Testing (Germany)<br />
In context with disposal container safety assessment of containers for radioactive waste the German Federal Institute for Materials<br />
Research and Testing (BAM) performed numerous drop tests in the last years. The tests were accompanied by extensive and<br />
various measurement techniques especially by instrumented measurements with strain gages and accelerometers.<br />
The instrumentation of a specimen is an important tool to evaluate its mechanical behavior during impact. Test results as deceleration-time<br />
and strain-time functions constitute a main basis for the validation of assumptions in the safety analysis and for the<br />
evaluation of calculations based on finite-element methods. Strain gauges are useful to determine the time dependent magnitude of<br />
any deformation and the associated stresses. Accelerometers are widely used for the measuring of motion i.e. speed or the displacement<br />
of the rigid cask body, vibration and shock events. In addition high-speed video technique can be used to visualize and analyze<br />
the kinematical impact scenario by motion analysis.<br />
The paper describes some selected aspects on instrumented measurements and motion analysis in context with low level<br />
radioactive waste (LLW) container drop testing.<br />
12) REGULATORY CLEARANCE OF SPENT STEEL DRUMS (wP-59405)<br />
Dae-Seok Hong, Korea Atomic Energy Research Institute; Young-Yong Ji, Il-Sik Kang,<br />
Kyoung-Kil Kwak, Woo-Seog Ryu, KAERI (Korea)<br />
At KAERI(Korea Atomic Energy Institute), radioactive soil and concrete wastes with extremely low level of activity were regulatory<br />
cleared in 2008 and large amount of spent drums were remained. After generation, drums having good physical integrity<br />
were reused for packaging radioactive wastes and about 50 tons of drums unsuitable for reuse were stored as radioactive wastes.<br />
Once having been used for packaging regulatory cleared radioactive wastes, these spent drums were determined to be cleared.<br />
Before clearance, steel drums were radiation monitored, washed with pressurized water two times, compacted and stored at a designated<br />
area. Based on radiological dose assessment result using a clearance scenario, the clearance of steel drums was permitted<br />
by the regulatory body. And then, treatment of the cleared drums was committed to a scrap-metal dealer for recycling. In this study,<br />
a process of the regulatory clearance for spent steel drums and a modified radiological dose assessment model for the scrap-metal<br />
dealer will be discussed.<br />
13) LIQUID WASTE TREATMENT PROCESS (w/oP-59061)<br />
Bouchta Moussaif, Touria Lambarki el Allioui, CNESTEN (Morocco)<br />
The law defined the responsibilities of the national center of nuclear energy in Morocco CNESTEN as the sole radioactive<br />
waste operating organization and designated CNESTEN as responsible for the management of radioactive waste at the national<br />
level in several social and economic sectors.<br />
The goals of the unit of radioactive waste management are: -reduce the volume of the radioactive waste product; -convert the<br />
radioactive waste into an appropriate waste for monitoring, storage and evacuation; -Recover if it’s possible an element of value.<br />
The Moroccan products of radioactive liquid waste per year are 0.1m3 of organic liquid and 35 m3 of liquid aqueous. The<br />
method adopted by CNESTEN was the evaporator for liquid aqueous and the solidification with the activated carbon for the organic<br />
liquid. An evaporation installation to treat 5 m3 of aqueous liquid in each campaign, the volume of the sludge obtained is 200<br />
liters and 4800 liters of distillate water. Concerning the management system is plan to collect the liquid aqueous in tanks in the bottom<br />
of each nuclear installation. After characterization according to the technical specification of radioactive waste management<br />
nuclear installation, the waste is transported in an appropriate tank to the treatment building to be evaporated. After treatment the<br />
clean water is collect in a separate tank waiting its discharge if it complies with the requirements of release. The volume of sludge<br />
issued from evaporator is conditioning with mortar (40 liters) in 120liters drum, the mixing operation is ensured by shingles introduced<br />
in the drum and the rotation of the drum is ensured by a mixer named “turn drums”. The drum must respect the acceptance<br />
criteria before transferred to storage building. About the liquid organic waste was collected in the polyethylene move tank; this kind<br />
of waste is mixed to an absorbent product and conditioned like the sludge.<br />
14) CAST IRON TRANSPORT, STORAGE AND DISPOSAL CONTAINERS FOR<br />
USE IN UK NUCLEAR LICENSED SITES (w/oP-59412)<br />
Joerg Viermann, Matthias P Messer, GNS Gesellschaft fuer Nuklear-Service mbH (UK)<br />
Ductile Cast Iron Containers of the types GCVI (UK trademark -GNS YELLOW BOX®) and MOSAIK® have been in use in<br />
Germany for transport, storage and disposal of intermediate level radioactive waste (ILW) for more than two decades. In 2009 a<br />
number of containers of these types were delivered to various Magnox sites as so called pathfinders to test their suitability for Magnox<br />
waste streams. The results were encouraging. Therefore the Letter of Compliance (LoC) procedure was started to prove the<br />
suitability of packages using these types of containers for the future UK Geological Disposal Facility (GDF) and a conceptual Letter<br />
of Compliance (cLoC) was obtained from RWMD in 2010. Waste stream specific applications for Interim Stage Letters of Compliance<br />
(ILoC) for a number of waste streams from different Magnox sites and from the UKs only pressurised water reactor,<br />
Sizewell B are currently being prepared and discussed with RWMD.<br />
In order to achieve a package suitable for interim storage and disposal the contents of a Ductile Cast Iron Container only has<br />
to be dried. Mobile drying facilities are readily available. Containers and drying facilities form a concerted system.<br />
During treatment, interim storage and transport the containers provide shielding and structural integrity….<br />
15) OPTIMIZATION OF RADIOACTIVE WASTE CEMENTATION FOR<br />
DECOMMISSIONING OF SALASPILS RESEARCH REACTOR (wP-59066)<br />
Gunta Abramenkova, Maris Klavins, University of Latvia; Andris Abramenkovs,<br />
Latvian Environment, Geology and Meteorology Centre (Latvia)<br />
This paper deals with information on the radioactive waste cementation technology for decommissioning of Salaspils Research<br />
67
Session 9 Abstracts<br />
Reactor (SRR). Dismantled and segmented radioactive materials were cemented in concrete containers using tritiated water-cement<br />
mixture. The viscosity of water-cement mortar, mechanical tests of solidified mortar’s samples, change of temperature of the samples<br />
during solidification time and long time leakage of 137Cs, 14C, 60Co and 3T radionuclides was studied for different watercement<br />
compositions with additives. The pH and electro conductivity of the solutions during leakage tests were controlled.<br />
It was shown, that water/cement ratio significantly influences on water-cement mortar’s viscosity and solidified samples<br />
mechanical stability. The role of additives – fly ash and Penetron admix in reduction of solidification temperature is discussed. It<br />
was found, that addition of fly ash to the cement-water mortar can reduce the solidification temperature from 81oC up to 62oC. The<br />
optimal interval of water ratio in cement mortar is discussed.<br />
Radionuclides leakage tests show that the release curves has a complicate structure. The possible radionuclides release mechanisms<br />
are discussed. Experimental results indicated that additives can significantly influence on the radionuclides release processes<br />
from cemented samples.<br />
The optimization of cementation of radioactive wastes in concrete containers was performed using mechanical stability, solidification<br />
temperature, radionuclide releases and viscosity of mortar.<br />
16) BAYESIAN STATISTICS APPLIED TO THE ACTIVITIES OF WASTE DRUMS (wP-59081)<br />
Richard Bull, Ian Adsley, Nuvia Limited (UK)<br />
Gamma spectrometry is widely used to determine the radioactive content of waste drums. However, the results of such surveys<br />
often result in large numbers of limit-of-detection (LOD) results. In a previous paper it was shown how simple statistical methods<br />
could be used to make estimates of the mean activity of a set of waste drums even when the individual measurements were dominated<br />
by limit-of-detection results. In that approach it was necessary to make assumptions about the statistical distribution (taken<br />
to be lognormal) of the activities and the geometric standard deviations of the distributions.<br />
In this paper a development of the method is presented which uses two statistical methods- Bayes’ Theorem and marginalization.<br />
These allow the probability distribution of the mean activity of the waste drums to be calculated, whilst the number of assumptions<br />
is reduced to just one, namely the form of the statistical distribution.<br />
The mathematical details are described in the paper and the application to a set of U235-in-drum measurements is presented.<br />
17) PHYSICAL MODELLING OF TURBULENT JETS FOR NUCLEAR SLUDGE MOBILISATION (wP-59147)<br />
Donna McKendrick, Institute of Particle Science and Engineering; Simon Biggs,<br />
Michael Fairweather, James Young, University of Leeds (UK)<br />
In the UK the Office for Nuclear Regulation and the Environment Agency developed the Generic Design Assessment process<br />
in response to a request from the UK Government. The process allows the regulators to jointly assess new nuclear reactor designs,<br />
in advance of any site-specific proposals to build a nuclear power station.<br />
Two reactor types are currently being assessed within Generic Design Assessment:<br />
• AREVA and Electricité de France's UK EPR®<br />
• Westinghouse Electric Company's AP1000®<br />
This paper will present the outcome of the assessment of radioactive waste management within the Generic Design Assessment<br />
process. One aspect of particular interest is the management of spent fuel from proposed new reactors as the assessment is<br />
based on an assumption that it will be sent for disposal. Therefore the paper will specifically consider the management of spent fuel<br />
and how this affects the regulatory decisions. The paper will look at four aspects. The first of these is to give a short overview of<br />
the Generic Design Assessment process. This will be followed by a summary of the Generic Design Assessment Radioactive Waste<br />
Management assessment on the acceptability of:<br />
• The types of waste and spent fuel<br />
• The plans for conditioning of the wastes<br />
• The safety issues associated with short-term storage.<br />
• The safety issues associated with long-term storage.<br />
• The issues associated with the disposal of the wastes.<br />
• The safety issues associated with decommissioning the reactors.<br />
The third aspect will be to look at the work commissioned by...<br />
18) ENVIRONMENTALLY-FRIENDLY RECOVERY OF URANIUM FROM NUCLEAR FUEL<br />
SCRAPS GENERATED AT NUCLEAR FUEL FABRICATION PROCESS (wP-59383)<br />
Kwang-Wook Kim, Dong-Yong Chung, Eil-Hee Lee, Keun-Young Lee, Kune Woo Lee,<br />
Jei-Kwon Moon, Korea Atomic Energy Research Insititute (Korea)<br />
A way to recover pure uranium as UO4 from UO2 and (U,Gd)O2 nuclear fuel scraps by using carbonate solution with hydrogen<br />
peroxide was studied and the nuclear fuel fabrication characteristics of the UO2 powder prepared from the UO4 was evaluated.<br />
19) SELF CLEANING HEPA FILTRATION WITHOUT INTERRUPTING PROCESS FLOW (wP-59347)<br />
Chris Chadwick, Porvair Filtration Group (UK)<br />
The strategy of protecting the traditional glass fibre HEPA filtration train from its blinding contamination and the recovery of<br />
dust by the means of self cleaning, pre-filtration is a proven means in the reduction of ultimate disposal volumes and has been used<br />
within the Fuel Production Industry.<br />
However, there is an increasing demand in nuclear applications requiring elevated operating temperatures, fire resistance,<br />
moisture resistance and chemical composition that the existing glass fibre HEPA filtration cannot accommodate, which can be<br />
remedied by the use of a metallic HEPA filter media.<br />
Previous research (Bergman et al 1997, Moore et al 1992) suggests that the then costs to the DOE, based on a five year life<br />
cycle, was $29.5 million for the installation, testing, removal and disposal of glass fibre HEPA filtration trains. Within these costs,<br />
$300 was the value given to the filter and $4,450 was given to the peripheral activity.<br />
68
Abstracts Session 9<br />
Development of a low cost, cleanable, metallic, direct replacement of the traditional filter train will the clear solution. The<br />
Bergman et al work has suggested that a 1000 ft^3/min, cleanable, stainless HEPA could be commercially available for $5,000 each,<br />
whereas the industry has determined that the truer cost of such an…<br />
20) STEAM AND CONDENSATE TOLERANT HEPA FILTER - SUBSTITUTE FOR ESP (wP-59346)<br />
Chris Chadwick, Porvair Filtration Group (UK)<br />
A major component has failed in an active vessel ventilation system, which has been running successfully for the last 25 years<br />
or so. The failed component is one of two Electrostatic Precipitators housed in a sealed concrete cell. The remaining running ESP<br />
could fail at any time. The systems overall clean-up capability has to be restored. A solution has been determined by the use of a<br />
bespoke metal filter unit. The discussion presents the issues and challenges associated with the solution.<br />
21) STATUS OF SITE INVESTIGATION FOR L/ILW FACILITIES IN THE PHILIPPINES (wP-59262)<br />
Maria V. Palattao, Carl Nohay, Rolando Reyes, Alfonso Singayan, Philippine Nuclear Research Institute (Philippines);<br />
Dirk Mallants, Belgian Nuclear Research Centre SCK-CEN (Belgium)<br />
Radioactive waste in the Philippines is generated from the various applications of radioactive materials in medicine, industries<br />
and research. The Philippine Nuclear Research Institute (PNRI) currently manages these wastes through its centralized treatment<br />
and storage facilities on site. Radioactive wastes that are received at the Institute are of different types ranging from contaminated<br />
solid and liquid materials to spent sealed sources, including radium. Treated and conditioned wastes are temporarily stored in simple<br />
roofed above ground concrete bunkers. The Philippine government through the Inter-agency Subcommittee on Radioactive<br />
Waste Management is committed to the development of a national repository for the countrys radioactive waste. This policy has<br />
been recognized in spite of the relatively small volume of radioactive waste compared with countries that have a nuclear power program.<br />
To date, a potential site has been identified for detailed investigation with the assistance of the International Atomic Energy<br />
Agency (IAEA). The site is located in the northern part of the Philippine archipelago and has about 34 hectares for potential development.<br />
A drilling program that aimed to investigate the geologic, hydrogeologic and hydrologic properties of the site has been<br />
implemented. All boreholes have been equipped with piezometer wells to continuously monitor the seasonal variation…<br />
22) MANAGEMENT OF SMOKE DETECTORS CONTAINING RADIOACTIVE SOURCES (wP-59049)<br />
Mercedes Salgado Mojena, Juan Carlos Benitez Navarro, Juan Miguel Hernandez García, Rafael Castillo Gomez,<br />
Ania Berdellans Escobar, CPHR (Cuba); Carlos Jose Pirez, Pedro Graciano Soto, Atomic Centre Ezeiza,<br />
National Commission of Atomic Energy (Argentina)<br />
Ionic smoke detectors contain radioactive sources that could be of Am-241, Pu-238, Pu-239, Kr-85, or other radionuclides.<br />
Although the activity of these devices is very low, their distribution and use is under regulatory control, and when become disused,<br />
should be managed as radioactive waste. More than 25 000 smoke detectors have been collected and stored at the Centralized Waste<br />
Management Facility in Cuba.<br />
The safe management of ionic smoke detectors consists in dismantling the devices, recovering the radioactive sources and conditioning<br />
them for long term storage and future disposal. Most of smoke detectors contain long lived radioactive sources (Am-241,<br />
Pu-238 and Pu-239), therefore especial attention is given to the management of these sources. The rest of nonradioactive materials<br />
are segregated (plastic, metal and electronic components) for recycling. A technical manual with specific instructions for all operations,<br />
including dismantling of detectors, segregation and management of non-active parts, recovering and conditioning of radioactive<br />
sources, has been developed.<br />
23) CURING TIME EFFECT ON THE FRACTION OF 137CS FROM IMMOBILIZED<br />
RADIOACTIVE EVAPORATOR SLUDGE BY CEMENT (wP-59006)<br />
Ilija Plecas, Slavko Dimovic, Vinca Institute of Nuclear Sciences; Radojica Pesic, Nuclear Facilities of Serbia (Serbia)<br />
Traditional methods of processing evaporator concentrates from NPP are evaporation and cementation.These methods allow to<br />
transform a liquid radioactive waste into the rather inert form, suitable for a final disposal. To assess the safety for disposal of<br />
radioactive mortar-waste composition, the leaching of 137Cs from immobilized radioactive evaporator concentrate into a surrounding<br />
fluid has been studied. Leaching tests were carried out in accordance with a method recommended by IAEA. Curing conditions<br />
and curing time prior to commencing the leaching test are critically important in leach studies since the extent of hydration of the<br />
cement materials determines how much hydration product develops and whether it is available to block the pore network, thereby<br />
reducing leaching. Incremental leaching rates Rn(cm/d) of 137Cs from evaporator concentrates after 180 days were measured. The<br />
results presented in this paper are examples of results obtained in a 20-year concrete testing project which will influence the design<br />
of the engineer trenches system for future central Serbian radioactive waste storing center.<br />
Key words : Cement, Radioactive Waste, Radionuclide, Leaching, concrete<br />
24) AN APPROACH FOR THE DEVELOPMENT OF A COMPREHENSIVE DATA BASE OF TIME-DEPENDENT<br />
HYDRAULIC AND TRANSPORT PARAMETERS FOR CONCRETE ENGINEERED BARRIERS (wP-59299)<br />
Suresh Seetharam, Dirk Mallants, Janez Perko, Diederik Jacques, SCK.CEN (Belgium)<br />
This paper presents an approach for the development of a comprehensive data base of time-dependent hydraulic and transport<br />
parameters for concrete engineered barriers and multi-layer cover of the future Dessel near surface repository. The parameter derivation<br />
is based on an extensive literature review, experimental data from studies on cementitious materials specific for the Dessel<br />
repository and numerical modelling studies. Best estimate parameter values for assessments are derived; source range and expert<br />
range are also determined, together with probability density functions. Emphasis is also given to the upscaling of laboratory derived<br />
parameter values to the repository component scale resulting in large-scale effective parameters. To accommodate different levels<br />
of conservatism in the various assessment calculations defined by ONDRAF/NIRAS, several sets of parameter values have been<br />
derived based on assumptions that introduce different degrees of conservatism. For pertinent parameters, the time evolution of such<br />
properties due to the long-term concrete degradation is also addressed. The implementation of the approach is demonstrated by considering<br />
diffusion coefficient as an example.<br />
69
Session 10 Abstracts<br />
25) RADIATION PROTECTION EXPERIENCES IN RETRIEVAL OF RADIOACTIVE<br />
WASTE AT PÜSPÖKSZILÁGY REPOSITORY (wP-59054)<br />
László Juhász, National Research Institute for Radiobiology and Radiohygiene; Sándor Kapitány,<br />
István Barnabás, Public Limited Company for Radioactive Waste Management;<br />
Anna Mária Motoc, National Research Institute for Radiobiology and Radiohygiene (Hungary)<br />
The radioactive waste disposal facility at Püspökszilágy is declared for disposal of institutional radioactive waste from smallscale<br />
producers in Hungary run by the Public Limited Company for Radioactive Waste Management (PURAM). The repository was<br />
sited in 1971 and commissioned in 1976. The repository is a typical near-surface facility, composed of concrete vaults and special<br />
disposal units.<br />
Because the original licence did not deal with waste acceptance criteria high activity sources and spent sealed radioactive<br />
sources (SSRS) consisting of long-half life and alpha emitting radionuclides were also disposed of. The results of the safety assessments<br />
clearly indicate that the SSRS could result in high doses to individuals who intrude into the facility after the closure and they<br />
could also lead to high doses following any future disruption of the facility by natural processes. Therefore the PURAM launched<br />
a demonstration program for retrieval and removal these radiation sources.<br />
The main aim of the achievement of the demonstration program was that each step of the recovery technologies could be appropriately<br />
tested before starting the full scale retrieval program. Concerning the high level activities of radiation sources and much<br />
elevated radiation fields the demonstration program had to be concerned from the radiation protection…<br />
SESSION 10 — PANEL: EMERGING ISSUES IN THE MANAGEMENT OF I/ILW (1.16)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 11 — PANEL: HOW CAN NETWORKS IMPROVE THE IMPLEMENTATION OF ER PROJECTS?<br />
THE IAEA NETWORK ON ENVIRONMENTAL MANAGEMENT AND REMEDIATION-ENVIRONET (4.15)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 12 — WASTE MINIMIZATION, AVOIDANCE, AND RECYCLING (1.3)<br />
1) WASTE MINIMIZATION BY MELTING - RECYCLING OF RADIOACTIVE METALS (wP-59040)<br />
Thomas Kluth, Ulrich Quade, Siempelkamp Nukleartechnik GmbH (Germany)<br />
Preserving resources is the fundamental principle for recycling of waste metals, using it as raw material for new products.<br />
Recycling radioactive metal waste from operational and decommissioned nuclear facilities meets this principle and minimizes the<br />
volume of radioactive waste and consequently saves costs.<br />
For 20 years now, the operation of the melting plant CARLA (Centrale Anlage zum Recyclieren Leichtaktiver Abfälle / central<br />
plant for recycling slightly radioactive waste) alongside the production facilities of the Siempelkamp foundry have delivered<br />
this service with plant licensed for handling radioactive material according to § 7 StrlSchV (the German radiation protection ordinance).<br />
The flexible nature of the facilities and products even allow metals that cannot be released after the primary melt, to be<br />
recycled into components used in nuclear industry, e. g. waste containers made of cast iron or heavy concrete. These recycling<br />
routes are unique in the world and were developed by Siempelkamp in the 1980ies and have been expanded continuously since<br />
then.<br />
More than 5,500 waste containers manufactured from Ductile Cast Iron (DCI) in cylindrical or cubic form licensed for the German<br />
ILW waste repository KONRAD have been manufactured with a recycled metal content of between 15 % and 25 %. Waste<br />
metals…<br />
2) WASTE MINIMIZATION BENEFITS OF DISSOLVABLE PROTECTIVE CLOTHING (wP-59003)<br />
Michael Cournoyer, David Wannigman, Robert Dodge, Los Alamos National Laboratory (USA)<br />
<strong>Program</strong>matic operations at the Los Alamos National Laboratory Plutonium Facility (TA-55) involve working with various<br />
amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne<br />
contamination, and excursions of contaminants into the operators breathing zone are controlled through the radiological protection<br />
program. A key element of this program is the proper selection of protective clothing. Re-useable, launderable protective<br />
clothing has been the standard for several decades. Over the years, radioactive waste disposal costs have increased and disposal<br />
options have become more limited. This has prompted the development of single-use, dissolvable protective clothing. Single-use,<br />
dissolvable protective clothing is under evaluation as a replacement for launderable woven textile garments at TA-55. We examined<br />
re-useable, launderable and single-use, dissolvable protective clothing, addressed management issues (residual contamination,<br />
cost, environmental footprint, quality assurance), and waste minimization benefits. Replacement of launderable garments with single-use,<br />
dissolvable protective clothing improves the safety configuration of TA-55 by reducing LLW waste generation. Process<br />
improvements of this type contribute to LANLs scientific and technological excellence by increasing the Laboratorys operational<br />
safety.<br />
3) EVALUATION OF EXTERNAL EXPOSURE DURING BUILDING AND OPERATION OF CONCRETE BRIDGES<br />
CONSTRUCTIONS THAT REUSE THE CONDITIONALLY RELEASED STEELS (wP-59120)<br />
Michal Panik, Vladimir Necas, Slovak University of Technology (Slovakia)<br />
This paper presents ongoing results of the project presented at ICEM`10 related to the topics of reusing the conditionally<br />
released materials from decommissioning. The subject of the reuse of conditionally released materials in this case is modeling of<br />
bridge constructions which reuse the conditionally released steel in the form of reinforcement bars for the concrete bridges. A general<br />
approach for the project was presented at ICEM`10. The activities of the project continue in evaluating the individual effective<br />
doses from the external exposure based on reused conditionally released steels separately for public and for professionals (the inter-<br />
70
Abstracts Session 12<br />
nal exposure will be evaluated in next stages of the project). Evaluated scenarios are related to critical groups of professionals constructing<br />
the bridges (workers scenarios). The computer code VISIPLAN 3D ALARA 4.0 planning tool was used for the calculation<br />
of the individual effective dose for professionals. Various limits of the annual individual effective dose are used for the evaluation<br />
of calculation results. The aim of the ongoing modeling is to develop a set of data of maximal radioactivity concentration for<br />
individual radionuclides in the conditionally released steel used in the bridges model constructions in order not to exceed the limits<br />
for the individual effective dose.<br />
4) TREATMENT OF SPENT ACIDIC DECONTAMINANTS WITH A HIGH-EFFICIENCY<br />
CEMENTATION METHOD (wP-59063)<br />
Kou-Ming Lin, Ching-Tu Chang, Ming-Shin Wu, Wen-Chen Lee,<br />
Jen-Chieh Chung, Tsong-Yang Wei, Institute of Nuclear Energy Research (Taiwan)<br />
Metal scrap is a major waste generated from the decommissioning of nuclear facilities. Through a decontamination process,<br />
most of the metal scraps can be cleaned to meet the clearance level, which can then be reused or released according to the regulatory<br />
procedure. Usually, chemical processes will be used in the cleaning step. Phosphoric acid and fluoroboric acid are the typically<br />
used chemicals or decontaminants. Although the regeneration method could be applied to increase the lifetime of the decontaminant,<br />
its decontamination efficiency would decrease after 3 to 5 cycles. In addition, the contaminated nuclide such as Cs-137 is not<br />
easily removed during the regeneration process; it tends to accumulate slowly in the decontaminant. According to the ALARA principle,<br />
decontaminant must be replaced if its activity exceeds the regulatory level. As a result, significant amount of spent strong<br />
acid solution would be generated. The traditional way of treatment is to neutralize the acid solution with an alkaline solution. However,<br />
such method will produce large amount of sludge that requires further stabilization, which offsets the advantages of metal<br />
decontamination.<br />
A high-efficiency solidification method is developed and used to treat the spent phosphoric acid and fluoroboric acid solution<br />
in INER. The self-polymerization nature of<br />
5) METHODOLOGY FOR IDENTIFICATION OF CONDITIONALLY RELEASED MATERIALS FROM<br />
DECOMMISSIONING USING THE OMEGA CODE (wP-59175)<br />
Matej Zachar, Vladimír Daniaka, DECOM, a.s.; Vladimir Necas, Slovak University of Technology (Slovakia)<br />
The nuclear facility decommissioning process is characterized by production of large volume of radioactive materials to be<br />
managed. The materials with radioactivity slightly above the defined unconditional clearance levels could be released conditionally<br />
for a specified industrial application in accordance with beforehand developed scenario ensuring that the limits for radiation<br />
exposure of workers and public will not be exceeded.<br />
The paper presents the methodology for identifying and assessment of the physical and radiological parameters of material<br />
items suitable for using in defined scenarios of conditional reuse of materials resulting from the decommissioning process. The calculation<br />
of mentioned parameters is done by using the analytical code OMEGA with implemented calculation stream for evaluation<br />
the conditional release process.<br />
The necessary input parameters for the OMEGA code are maximum concentrations of each radionuclide in the conditionally<br />
released materials which do not cause the doses above the limit values for the possible scenarios of further use of materials outside<br />
the nuclear site. The examples of such scenarios are assessed and presented in other related papers proposed for the ICEM conference.<br />
Based on the inventory database of physical and radiological characteristics of decommissioned facility, the calculation algorithm<br />
separates the relevant material items with activity concentrations…<br />
6) IMPACT OF NUCLIDE VECTOR COMPOSITION CONTAINED IN CONDITIONALLY<br />
RELEASED STEEL REUSED IN MOTORWAY TUNNELS SCENARIO ON<br />
CALCULATED INDIVIDUAL EFFECTIVE DOSES (wP-59128)<br />
Tomas Hrncir, Vladimir Necas, Slovak University of Technology (Slovakia)<br />
This paper presents ongoing results of the project presented at ICEM 10 [paper 40071] related to the topics of the reuse of conditionally<br />
released materials arising from decommissioning of nuclear installations.<br />
The subject of the presented paper is modelling of motorway tunnels, which reuse the conditionally released steel in form of<br />
reinforcing nets and bars for the concrete construction of tunnels. The general approach for the project was presented at ICEM 10.<br />
The activities of the project continued in evaluating the impact of the nuclide composition contained in the conditionally released<br />
steel on calculated individual effective doses from the external exposure (the internal exposure will be evaluated in next stages of<br />
the project). Mentioned radioactive steel arises during decommissioning and would be reused in motorway tunnels. Evaluated scenarios<br />
are related to critical groups of public (drivers scenarios) and for professionals constructing the tunnels and performing the<br />
maintenance of tunnels (workers scenarios).<br />
The computer code VISIPLAN 4.0 3D ALARA planning tool was used for the calculation of individual effective doses for<br />
worker and for public groups. Various limits of the individual effective dose are used for public and for professionals. The aim of<br />
the ongoing modelling is to develop a set…<br />
7) EVALUATION OF TECHNICAL, ECONOMIC AND FINANCIAL FEASIBILITY FOR RECYCLING<br />
AND REPROCESSING OF RADIOACTIVE WASTE FROM A REMEDIATION WORK OF LOW<br />
AND MEDIUM ACTIVITY FOR THE EXTRACTION OF HEAVY MINERALS (w/oP-59231)<br />
Rodrigo Raposo de Almeida, Federal Fluminense University;<br />
Valter J.G. Mortágua, Industrias Nucleares do Brasil (Brazil)<br />
This paper aims to present the methodology and criteria used for the destination, discard and reuse of waste from the remediation<br />
activities of soil contaminated by radioactive waste of low activity in the USIN Plant. The site is located in São Paulo city,<br />
the city with the largest population of Brazil, with approximately 11 million inhabitants. As the environmental agency in São Paulo<br />
state, in this neighborhood there are several cases of severe contamination of soil and groundwater. The situation of contamination<br />
is so severe that it is forbidden the use of groundwater in the region for an indefinite period. Site of the plant running in a monazite<br />
71
Session 13 Abstracts<br />
processing plant for extraction of rare earths, have been filed across the land several fractions of soil containing monazite sand. In<br />
order to guide the remediation of the area for unrestricted use, was a plan for remediation of radioactive waste characterization<br />
based on geological, hydrogeological and environmental extensive in the area. From the calculation of the dose was established that<br />
the fractions of soil with concentrations of 226Ra and 228Ra below 0.5 Bq/g result in additional effective dose less than 1.0 mSv/yr<br />
and therefore can be kept on the ground. The fractions…<br />
8) WNA STATEMENT - TOWARDS GREATER EFFICIENCY IN THE MANAGEMENT<br />
OF LOW-LEVEL RADIOACTIVE MATERIAL THAT CONCURRENTLY SUPPORTS REUSE,<br />
RECYCLING AND DISPOSAL (wP - 59414)<br />
Sylvain Saint-Pierre, World Nuclear Association (WNA) (UK)<br />
This paper presents the subject WNA statement which resulted from a conserted effort between a wide range of nuclear industry<br />
players such as nuclear power utilities, nuclear fuel cycle companies – and experienced recyling and waste disposal companies<br />
which routinely received material from nuclear sites.<br />
SESSION 13 — HLW, FISSILE, TRU AND SPENT FUEL SHORT AND LONG-TERM STORAGE ISSUES (2.4)<br />
1) WEST VALLEY DEMONSTRATION PROJECT HIGH LEVEL, TRANSURANIC,<br />
AND GREATER THAN CLASS C WASTES (wP-59048)<br />
James Blankenhorn, West Valley Environmental Services (USA)<br />
Located in the scenic hills of Western New York, just about 35 miles south of Buffalo, the 68 acre West Valley Demonstration<br />
Project (WVDP) is a unique and challenging environmental cleanup project that currently manages High Level, Transuranic, and<br />
Greater than Class C wastes<br />
Before the U.S. Department of Energy (DOE) took on the challenge of cleaning up the site, the site was the location of the only<br />
commercial spent nuclear fuel (SNF) reprocessing facility to operate in the United States. Operated by Nuclear Fuels Services from<br />
1966-72, the site was owned by the State of New York and licensed by the Atomic Energy Commission. During operations, the<br />
plant reprocessed approximately 640 metric tons of spent nuclear fuel. When commercial operations were discontinued and the<br />
facilities were returned to New York State, there were nearly 2,271,247 liters (nearly 600,000 gallons) of liquid high-level radioactive<br />
waste (HLW) in an underground storage tank and the facility that was used to reprocess the SNF, the Main Plant Process Building<br />
(MPPB), was highly contaminated.<br />
The West Valley Demonstration Project Act of 1980 (the Act) authorized DOE to conduct a cleanup of the site, in cooperation<br />
with the New York State Energy Research and Development…<br />
2) MANAGING AGING EFFECTS ON USED FUEL DRY CASK FOR VERY LONG-TERM STORAGE (wP-59067)<br />
Omesh Chopra, Dwight Diercks, David Ma, Vik Shah, Shiu-Wing Tam, Ralph Fabian,<br />
Yung Liu, Mark Nutt, Argonne National Laboratory (ANL)(USA)<br />
The cancellation of the Yucca Mountain repository program in the Unites States raises the prospect of very long-term storage<br />
(i.e., >120 years) of used fuel and deferred transportation. While long-term storage of used nuclear fuel in dry cask storage systems<br />
(DCSSs) at Independent Spent Fuel Storage Installations (ISFSIs) is already a standard practice among U.S. utilities, recent rulemaking<br />
activities of the U.S. Nuclear Regulatory Commission (NRC) indicated additional flexibility for the NRC licensees of ISF-<br />
SIs and certificate holders of the DCSSs to request initial and renewal terms for up to 40 years. The proposed rule also adds a<br />
requirement that renewal applicants must provide time-limited aging analyses (TLAAs) and descriptions of aging management programs<br />
(AMPs) to ensure that the systems, structures, and components (SSCs) in the DCSSs will perform as designed under the<br />
extended license terms. Details of the license renewal process can be found in the NRC draft Standard Review Plan (NUREG-1927)<br />
for renewal of ISFSI Licenses and DCSS Certificates of Compliance (CoCs). The final Standard Review Plan will provide NRC<br />
staff with guidance on the renewal of site-specific licenses and CoCs.<br />
Over the last three decades, Argonne National Laboratory has conducted research programs funded by NRC to address…<br />
3) APPLICATION OF COUPLED THERMO-HYDRO-MECHANICAL-CHEMICAL (THMC) PROCESS IN<br />
HYDROTHERMAL SYSTEMS TO PROCESS NEAR A HIGH-LEVEL NUCLEAR WASTE REPOSITORY (wP-59246)<br />
Geoffrey Peter, Oregon Institute of Technology Portland Center (USA)<br />
Modeling of coupled processes in the geology near a high-level nuclear waste repository is similar to the modeling of coupled<br />
Thermo-Hydro-Mechanical-Chemical (THMC) processes that occur in magma-hydrothermal systems. Magma-hydrothermal systems<br />
were extensively studied by former Professor Denis Norton and his colleagues at the Geoscience Department at University of<br />
Arizona. These hydro-thermal codes were verified by obtaining excellent matches between calculated oxgyen 18 isotope - values<br />
and measured oxygen 18 isotope values in three principal rock units: basalt, gabbro, and gneiss.<br />
This paper reviews the concept of transport theory used in the formulation of the conservation principle that is used to model<br />
the hydrothermal systems. In addition, it reviews conservation of mass, momentum, energy, and chemical components equations as<br />
applied to the multicomponent-multiphase systems related to hydrothermal systems and obtains parallels to reaction rates and<br />
radionuclide transport in the geology of a high level nuclear water repository. The paper discusses the numerical methods used to<br />
solve the coupled equations.<br />
Further, this paper compares published results obtained by other researchers modeling coupled THM process in the geology of<br />
high-level nuclear waste repositories.<br />
72
Abstracts Session 13<br />
4) GENERIC DESIGN ASSESSMENT OF LONG-TERM SPENT FUEL STORAGE<br />
FOR NEW REACTORS IN THE UK (wP-59174)<br />
Christopher Fisher, Nuclear Directorate, Health and Safety Executive;<br />
Dave Watson, Office of Nuclear Regulation; Ian Streatfield, Colette Grundy,<br />
Saffron Price-Walter, Environment Agency, Dave Glazbrook, Office of Nuclear Regulation (UK)<br />
In the UK the HSE and the Environment Agency developed the Generic Design Assessment or GDA process in response to a<br />
request from the UK Government. The process allowed the regulators to jointly assess new nuclear reactor designs, in advance of<br />
any site-specific proposals to build a nuclear power station. The first GDA process will be complete in June 2011.<br />
Two reactor types are being assessed within GDA:<br />
• AREVA and Electricité de France’s (EDF) UK EPR®<br />
• Westinghouse Electric Company’s AP1000®<br />
This paper will present the outcome of the assessment of radioactive waste management and decommissioning (RW&D)<br />
within the GDA process. One of the most interesting aspects is the management of spent fuel as it is assumed that this will be<br />
sent for disposal. Therefore the presentation will specifically consider the management of spent fuel and how this affects the<br />
reulatory decisions.<br />
The presentation and paper will look at four aspects. The first of these is to give a short overview of the GDA process.<br />
This will be followed by a summary of the regulators conclusions at the end of GDA on the acceptability of:<br />
• The types of waste and spent fuel<br />
• The plans for conditioning of…<br />
6) INDUSTRIAL COMPLEMENTARITIES BETWEEN INTERIM STORAGE AND<br />
REVERSIBLE GEOLOGICAL REPOSITORY (wP-59237)<br />
Jean-Michel Hoorelbeke, Andra (France)<br />
The French Act voted in 2006 made the choice of deep geological disposal as the reference option for ILW and HLW long term<br />
management. The CIGEO repository project aims at avoiding or limiting burden to future generations, which could not be achieved<br />
by the extension in time of interim storage. The reversibility as provided by the Act will maintain a liberty of choice for waste management<br />
on a duration which is comparable to new storage facility.<br />
Interim storage is required to accommodate waste as long as the repository is not available. The commissioning of the repository<br />
in 2025 will not suppress needs for interim storage. The paper describes the complementarities between existing and future<br />
interim storage facilities and the repository project: repository operational issues and planning, HLW thermal decay, support for the<br />
reversibility, etc. It shows opportunities to prepare a global optimization of waste management including the utilization at best of<br />
storage capacities and the planning of waste emplacement in the repository in such a way to facilitate operational conditions and<br />
to limit cost. Preliminary simulations of storage-disposal scenarios are presented.<br />
Thanks to an optimal use of the waste management system, provision can be made for a progressive increase of…<br />
7) RECENT DEVELOPMENTS IN SPENT FUEL MANAGEMENT IN NORWAY (wP-59260)<br />
Peter Bennett, Barbara Oberlander, Erlend Larsen, Institutt for Energiteknikk (Norway<br />
Spent Nuclear Fuel (SNF) in Norway has arisen from irradiation of fuel in the NORA, Jeep I and Jeep II reactors at Kjeller,<br />
and in the Heavy Boiling Water Reactor (HBWR) in Halden. In total there is some 16 tonnes of SNF, with 12 tonnes of aluminium-clad<br />
fuel, of which 10 tonnes is metallic uranium fuel and the remainder oxide (UO2). The portion of this fuel that is similar to<br />
commercial fuel (UO2 clad in Zircaloy) may be suitable for direct disposal on the Swedish model or in other repository designs.<br />
However, metallic uranium and/or fuels clad in aluminium are chemically reactive and there would be risks associated with direct<br />
disposal.<br />
Two committees were established by the Government of Norway in January 2009 to make recommendations for the interim<br />
storage and final disposal of spent fuel in Norway. The Technical Committee on Storage and Disposal of Metallic Uranium Fuel<br />
and Al-clad Fuels was formed with the mandate to recommend treatment (i.e. conditioning) options for metallic uranium fuel and<br />
aluminium-clad fuel to render them stable for long term storage and disposal. This committee, whose members were drawn from<br />
the nuclear industry, reported in January 2010, and recommended commercial reprocessing as the<br />
8) ADVANCED SURVEILLANCE TECHNOLOGIES FOR USED FUEL<br />
LONG-TERM STORAGE AND TRANSPORTATION (wP-59032)<br />
Hanchung Tsai, Yung Liu, Mark Nutt, Argonne National Laboratory; James Shuler, US Department of Energy (USA)<br />
Dry cask storage systems are being used by utilities in the United States to handle the ever-increasing number of discharged<br />
fuel assemblies from nuclear power plants. Most of the newer systems incorporate multiple-purpose (storage, transport, and disposal)<br />
or dual-purpose (storage and transport) canister technologies. With the prospect of very long-term storage (>120 years) and<br />
deferred transport looming, condition- and performance-based aging management of structures and components in the dry cask<br />
storage systems becomes an even more challenging task. From the standpoint of used fuels, one of the greatest concerns is embrittlement-related<br />
cladding rupture of a large number of used fuel rods during long-term storage and transportation.<br />
Radio frequency identification (RFID) is an automated and remote-sensing technology ideally suited to monitor sensitive assets<br />
on a continuous, long-term basis. One such system, called ARG-US, has been developed by Argonne National Laboratory for the<br />
U.S. Department of Energy Packaging Certification <strong>Program</strong>, Office of Packaging and Transportation, and deployed at several DOE<br />
sites to track and monitor drums containing nuclear and radioactive materials. While the sensor suite currently in the ARG-US RFID<br />
tags (seal, temperature, humidity, shock and radiation) is adequate in monitoring the exterior conditions of the used fuel casks,<br />
advanced surveillance technology<br />
73
Session 14 Abstracts<br />
SESSION 14 — D&D OF POWER REACTORS AND RESEARCH REACTORS (3.9)<br />
1) DFD AN APPROACH TO NEW REACTOR DESIGNS (wP-59197)<br />
Jas S. Devgun, Sargent & Lundy (USA)<br />
Design for Decommissioning (DfD) is now becoming a part of the design optimization process for the new reactor designs.<br />
This is a significant contrast to when the currently operating reactors were designed several decades ago and when decommissioning<br />
was not given much thought during the design process. At a time when nuclear renaissance has taken hold worldwide and many<br />
reactors are in the planning or early construction stages, design considerations for decommissioning will have a significant impact<br />
not only during the construction but also during the eventual decommissioning phase albeit long after the design stage as most reactors<br />
are now designed for 60 year operating life.<br />
Industry has taken a lead in this area and all current designs incorporate decommissioning considerations into the designs of<br />
the new reactors to some degree. Some, such as, AP1000 are highly optimized in this regard. The goals are to have fewer components,<br />
provide for modular designs for construction and eventual deconstruction, address major component removal issues, minimize<br />
the generation of radioactive waste, and provide for better radiological safety.<br />
International interest in the area has culminated in new or updated guidance on the subject at the IAEA and NEA. The IAEA<br />
has drafted a technical…<br />
2) FEEDBACK FROM WESTINGHOUSE EXPERIENCE ON SEGMENTATION<br />
OF REACTOR VESSEL INTERNALS (wP-59013)<br />
Joseph Boucau, Westinghouse Electric Company; Stefan Fallström, Westinghouse;<br />
Per Segerud, Westinghouse Electric Sweden; Paul Kreitman, Westinghouse Electric Company (Belgium/Sweden/USA)<br />
With more than 20 years of experience in the development of reactor vessel internals segmentation and packaging technology,<br />
Westinghouse has accumulated significant know-how in the reactor dismantling market.<br />
Building on tooling concepts and cutting methodologies developed decades ago for the successful removal of nuclear fuel from<br />
the damaged Three Mile Island Unit 2 reactor (TMI-2), Westinghouse has continuously improved its approach to internals segmentation<br />
and packaging by incorporating lessons learned and best practices into each successive project.<br />
Westinghouse has developed several concepts to dismantle reactor internals based on safe and reliable techniques, including<br />
plasma arc cutting (PAC), abrasive waterjet cutting (AWJC), metal disintegration machining (MDM), or mechanical cutting. Westinghouse<br />
has applied its technology to all types of reactors covering Pressurized Water Reactors (PWRs), Boiling Water Reactors<br />
(BWRs), Gas Cooled Reactors (GCRs) and sodium reactors.<br />
The primary challenges of a segmentation and packaging project are to separate the highly activated materials from the lessactivated<br />
materials and package them into appropriate containers for disposal. Since space is almost always a limiting factor it is<br />
therefore important to plan and optimize the available room in the segmentation areas.<br />
The choice of the optimum cutting technology is important for a successful project implementation and…<br />
3) UPDATE ON JOSE CABRERA NPP DECOMMISSIONING (wP-59322)<br />
Juan Santiago, Nieves Martin, Manuel Rodriguez, ENRESA (Spain)<br />
Construction of José Cabrera Nuclear Power Plant, owned by Gas Natural, began in 1964 and the plant went into commercial<br />
operation in 1969. The nuclear steam supply system was designed and supplied by Westinghouse and is made up of a light PWR<br />
reactor with an authorized thermal output of 510 MW and an electrical power of 160 MW and all the auxiliary and safety systems<br />
required for the efficient operation of the facility under safe conditions.<br />
In 2002, the Ministry of Economy authorized the operation of the plant until April 30th 2006. Subsequently, the Directorate<br />
General for Energy Policy and Mines, through of Order of April 20th 2006, confirmed the definitive shutdown of the plant on the<br />
schedule date and established the requirements to be met in performing activities at the facility prior to awarding of the dismantling<br />
permit, along with the basic framework for the granting of this authorization.<br />
On April 30th 2008, ENRESA requested the transfer of the ownership of the José Cabrera NPP from the Ministry of Industry,<br />
Tourism and Trade, along with the corresponding authorization for performance of the Dismantling and decommissioning Plan,<br />
submitting the documentation required by article 30 of the Regulation on Nuclear and…<br />
4) THE DECOMMISSIONING OF THE CIEMAT NUCLEAR RESEARCH CENTRE (w/oP-59321)<br />
Juan Santiago, Sergio Vidaechea, Manuel Ondaro, ENRESA (Spain)<br />
CIEMAT, formerly the Nuclear Energy Board (JEN), is the Spanish Centre for Energy-Related, Environmental and Technological<br />
Research. Located in Madrid, it used to have more than 60 facilities in operation that allowed a wide range of activities in the<br />
nuclear field and in the application of ionising radiations. Particularly significant among these facilities were the research reactors,<br />
particle accelerators, hot cells and nuclear fuel manufacturing and processing plants.<br />
At present the centre, which is authorised as a single nuclear facility, includes various installations, some of them are now obsolete,<br />
shut down and in dismantling phases. In 2000 CIEMAT started the Integrated plan for the improvement of CIEMAT installations<br />
(PIMIC), which includes activities for the decontamination, dismantling and rehabilitation of obsolete facilities.<br />
The PIMIC-Decommissioning Project, carried out by ENRESA as main contractor, includes the dismantling of 4 installations:<br />
JEN-1 Research Reactor, Reprocessing plant (Hot Cell M-1), Radioactive Liquid Treatment Plant and Radioactive Liquid Storage<br />
Plant. Besides, a small contaminated area has to be remediated and restored, because of an incidental leakage of radioactive liquid<br />
in the 70´s.<br />
Currently, decommissioning activities in buildings have been completed, and soil remediation is under way together with the<br />
final radiological characterisation of the soil, including…<br />
74
Abstracts Session 14<br />
5) THE REMOVAL, TRANSPORTATION AND FINAL TREATMENT AND CONDITIONING<br />
OF THE THETIS RESEARCH REACTOR SPENT FUEL OF THE UNIVERSITY<br />
OF GHENT (BELGIUM) ACHIEVED IN 2010 AUTHORS (wP-59261)<br />
Hubert Thierens, Myriam Monsieurs, Ghent University; Vincent De pooter, Marnix Braeckeveldt, NIRAS/ONDRAF;<br />
Luc Noynaert, SCK●CEN; Patrick Lewandowski, Belgoprocess; Patrick Maris, Luc Ooms, SCK●CEN; Karel Strijckmans, Ghent University (Belgium)<br />
The THETIS research reactor on the site of the Nuclear Sciences Institute of the Ghent University has been in operation from<br />
1967 until December 2003. This light-water moderated graphite-reflected low-enriched uranium pool-type reactor has been used<br />
for various purposes e.g. the production of radio-isotopes and activation analyses. During the first years its core power was 15 kW.<br />
In the early 70, a core enlargement allowed for operation at typically 150 kW, while the maximum was allowed to be 250 kW. The<br />
fuel was 5% enriched uranium cladded with AISI304L stainless steel, with graphite plugs at both end of the tubes.<br />
In order to decommission the reactor, the spent fuel and other nuclear materials present had to be removed from the reactor<br />
site.<br />
Ghent University entrusted to SCK”CEN, the Belgian Nuclear Research Centre , the study of the further management of the<br />
spent fuel. Various options such as reprocessing, intermediate storage awaiting final disposal were investigated. However the characteristics<br />
and the small amount of spent fuel made these solutions very expensive. In the meantime NIRAS/ONDRAF, the Belgian<br />
radioactive waste management agency, was developing together with Belgoprocess, a solution for final conditioning in 400<br />
liter drums and further intermediate storage of the…<br />
6) DECOMMISSIONING AND DISMANTLING OF THE FRENCH BRENNILIS NPP (w/oP-59366)<br />
Thierry Andre, ONET Technologies; Werner Botzem, Nukem Technologies (France/Germany)<br />
This paper deals with the dismantling of the Brennilis NPP plant located in the west of France (Finistère). This prototype NPP<br />
of Brennilis was the unique reactor of the heavy water developed in France during the 50 and the 60. The reactor diverged in<br />
December 1966 and the NPP was operated during 9 years from 1972 to 1981, then the permanent shutdown occurred in July 1985.<br />
In 2008, the operator and owner of the plant Electricité de France (EDF) commissioned consortium Onet Technologies (France)<br />
and Nukem Technologies (Germany) with the dismantling of the reactor block of the NPP.<br />
The reactor block essentially contains the reactor vessel including built-in units and biological shields, the peripheral piping as<br />
well as systems for controlling the nuclear-related process. In addition to the complete dismantling, the scope of the contractual<br />
services also includes their proper handling in accordance with the applicable regulation : safety requirements, waste management,<br />
radioprotection optimization and management.<br />
The central element of the plant is the reactor pressure vessel filled with heavy water. Each of the 216 horizontal fuel element<br />
channels made of zircaloy is at each side connected to a pipe which directs the heat transfer gas to a header mounted…<br />
7) THE CHOOZ A REACTOR DISMANTLING PROJECT (wP-59363)<br />
Estelle Grevin, EDF; Joseph Boucau, Westinghouse Electric Company (France/Belgium)<br />
Located in the Ardennes next to the Meuse River, Chooz A nuclear power plant was the first Pressurised Water Reactor (PWR)<br />
built in France (1963). Its a 305 MW NPP and it produced electricity from 1967 until 1991 (38TWh). Chooz A NPP was permanently<br />
shut down in 1993 and the fuel was removed.<br />
The complete dismantling decree was published in September 2007. According to this decree, the dismantling is spilt into 3<br />
main steps :<br />
1st step: dismantling of all the nuclear equipment (2008 to 2015)<br />
2nd step: tritium ratio decrease monitoring.(2015-2017)<br />
3rd step: dismantling of the equipment needed for gathering. Filling of the underground buildings with concrete.<br />
In 2010 the dismantling of the circuits connected to the vessel commenced. On Monday, the 1st of February, the first steam<br />
generator was extracted and prepared to be decontaminated. Steam generators and the primary circuit will be decontaminated before<br />
being transported in one piece to the French nuclear waste storage facility.<br />
Once the decontamination is complete, the vessel dismantling will begin: this will be another important step for the project.<br />
8) FULL SYSTEM DECONTAMINATION (FSD) PRIOR TO DECOMMISSIONING (wP-59189)<br />
Christoph Stiepani, AREVA NP GmbH (Germany)<br />
Decontamination prior to decommissioning and dismantling is imperative. Not only does it provide for minimization of personnel<br />
dose exposure but also maximization of the material volume available for free release. Since easier dismantling techniques<br />
in lower dose areas can be applied, the licensing process is facilitated and the scheduling and budgeting effort is more reliable.<br />
The most internationally accepted approach for decontamination prior to decommissioning projects is the Full System Decontamination<br />
(FSD). FSD is defined as the chemical decontamination of the primary cooling circuit, in conjunction with the main auxiliary<br />
systems.<br />
AREVA has long-term experience with Full System Decontamination for return to service of operating nuclear power plants<br />
as well as for decommissioning after shutdown. Since 1976, AREVA has performed over 500 decontamination applications and<br />
from 1986 on, decontaminations prior to decommissioning projects which comprise virtually all nuclear power plant (NPP) designs<br />
and plant conditions:<br />
• NPP designs: HPWR, PWR, and BWR by AREVA, Westinghouse, ABB and GE<br />
• Decontaminations performed shortly after final shutdown or several years later, and even after re-opening safe enclosure<br />
• High alpha inventory and or low gamma/alpha ratio<br />
• Main coolant chemistry (e.g. with and without Zn injection during operation)<br />
Fifteen decontaminations prior to…<br />
75
Session 15 Abstracts<br />
SESSION 15— THE FRENCH D&D ACTIVITIES - ORGANIZATION, STRATEGY,<br />
OBJECTIVES AND EXPERIENCE (3.2)<br />
1) CEA’S DECOMMISSIONING POLICY AND STRATEGIES. LESSONS LEARNED (w/oP-59203)<br />
Philippe Guiberteau, Didier Dall’ava, CEA; Jean-Guy Nokhamzon, CEA/DEN/DADN (France)<br />
Since the beginning of the 20th century, France has carried out research programmes on civil use of nuclear, and its application,<br />
France has set up and run various types of installations: research or prototypes reactors, process study or examination laboratories,<br />
pilot installations, accelerators, nuclear power plants and processing facilities. There are currently more than several tens of<br />
facilities which are presently closed down pending dismantling or in the process of being dismantled by CEA , the governmental<br />
body for research and development in nuclear and renewable energies..<br />
When operating, all these installations work with nuclear materials and generate radioactive waste. When they are shutdown,<br />
either as a result of the programmes for which they were set up, or due to equipment wearing out or being obsolete, these installations<br />
must be cleaned and dismantled, taking into account their nuclear nature and requirements related to safety and environment.<br />
During the decommissioning process, the implementer has to deal with safety and site rehabilitation issues.<br />
Dealing with these installations is a long-term programme which must be carefully planned and financed in order to optimise<br />
its management.<br />
The paper will describe the French decommissioning policy and strategies adopted, showing that :<br />
• Safety is guaranteed…<br />
2) CLEANSING AND DISMANTLING OF CEA-SACLAY NUCLEAR LICENSED FACILITIES (W/OP -59227)<br />
Michel K. Jeanjacques, Rebecca Glévarec, Isabelle Delaire,<br />
Jean Louis Martin, Commissariat à l’Energie Atomique et aux Energies Alternatives (France)<br />
This summary presents the cleansing and dismantling operations currently realized on the CEA center of Saclay (CEA-Saclay).<br />
This CEA center was created at the beginning of the Fifties on the plateau of Saclay located at approximately 25 km at the south<br />
of Paris. The CEA-Saclay as of its creation was dedicated to fundamental research, the studies for the development of the nuclear<br />
dies, the uranium enrichment and the radioelement study and production.<br />
The Saclay-center nuclear facilities were already dismantled in function of the end of R&D and fundamental research (research<br />
reactor: EL2-EL3, critical mock-up, uranium enrichment pilot plants, radioelement production cells, and accelerators SATURNE-<br />
ALS [Saclay Linear Accelerator]). It was initiated at the beginning of the 2000 years a cleansing and dismantling program of the<br />
old Nuclear Licensed Facilities (LNF). Currently this program relates to the Hot Laboratories (Laboratoires de Haute Activité :<br />
LHA) and the old workshops of the Liquid Waste Treatment Plant (Station des Effluents Liquides : STEL).<br />
The LHA are a multipurpose laboratory for R&D studies of various units of the CEA-Saclay. They were built at the end of the<br />
Fifties. The reference safety frame allowed disassembling the equipment at the end of R&D program. Since the beginning…<br />
3) DECONTAMINATION AND DISMANTLING OF CENDRILLON TRANSFER<br />
SYSTEMS FOR RADIOACTIVE LIQUID SOLUTIONS (w/oP -59336)<br />
Michel K. Jeanjacques, Commissariat à l’Energie Atomique et aux Energies Alternatives;<br />
Frédéric Masure, Alternative Energies and Atomic Energy Commission (France)<br />
The CENDRILLON system was studied and developed by the CEA at the end of the 1950s and early of the 1960s to transfer<br />
and transport the radioactive liquid solutions to waste treatment facilities. This system has been manufactured in several versions<br />
in three different sizes and for each different volumes of capacity. For each size, the biological shielding thickness is based on the<br />
volume capacity. Whatever the size and volume, the CENDRILLON connection system remains identical. All liquid transfers, filling<br />
and sucking out, of the CENDRILLON are carried under vacuum.<br />
The CENDRILLON D&D works are carried out during the facilities POCO (post clean out operations) and decommissioning<br />
or into a dedicated waste treatment plant.<br />
The parer will show CEAs procedure to carry out these CENDRILLON D&D works. It consists of tasks sequences: CEN-<br />
DRILLON emptiness assessment, capacity flushing and decontamination, pumping out, drying and finally CENDRILLON dismantling<br />
by mechanical disassembly (taking apart) and the capacity cutting. Control of nuclear risk is essential for all these tasks: radiolysis,<br />
contamination and irradiation.<br />
4) AREVA RETURN ON EXPERIENCE FROM D&D PROGRAMME MANAGEMENT -<br />
WHAT WE HAVE LEARNED SO FAR? (w/oP -59324)<br />
Jean-Michel Chabeuf, Thierry Varet, Grégoire de Laval, Guy Decobert,<br />
Frédéric Chambon, AREVA Nuclear Site Value Development BU (France)<br />
In November 1997, UP1, France first large scale reprocessing plant, ceased operations after 40 years of activities. A comprehensive<br />
D&D program was immediately initiated, scheduled to last for a period of approximately 30 years. In 2002, AREVA<br />
launched the decommissioning and dismantling of SICN sites, two GCR fuel fabrication located near Grenoble and Annecy. Shortly<br />
after, in 2003, the second reprocessing plant, UP2 400, commissioned in the sixties in La Hague (Normandy) followed. Less than<br />
a decade later, UP1 decommissioning program is well advanced, with the de-cladding facilities nearing completion, and the chemical<br />
plant showing a work progress of about 50%. The decommissioning of SICN sites is reaching its final stage, with concrete<br />
scrabbling operations launched in order to release the site for non nuclear industrial activities. A part of UP2 400 de-cladding facilities<br />
have been dismantled, and a vast D&D program is now on track for the bulk of the plant.<br />
AREVA is managing those operations, either as owner in La Hague and SICN, or as prime contractor for the French Atomic<br />
Energy commission in Marcoule.<br />
More than 10 years of continuous, large scale D&D operations have provided a unique feed back for such operations.<br />
RETURN ON EXPERIENCE OF…<br />
76
Abstracts Session 16<br />
SESSION 16 — NATIONAL AND INTERNATIONAL D&D PROGRAMS (3.3)<br />
1) PARTICULARITIES OF CHNPP SITE REMEDIATION DURING ITS DECOMMISSIONING (wP-59193)<br />
Sergii Mitichkin, Valeriy Seyda, Chernobyl NPP (Ukraine)<br />
On April 26, 1986 beyond designed accident occurred at Chernobyl NPPs Unit 4 as a result of which the reactor core and protective<br />
safety barriers have been destroyed. Releases of fission products are evaluated approximately in 50 MKu (without considering<br />
inert radioactive gases) that makes approximately 3,5 % of total quantity of the radio nuclides accumulated in the reactor as<br />
of the moment of accident.<br />
To liquidate the accident consequences it has been constructed the Shelter object. The major part of fission nuclear materials<br />
is localized within the Shelter object in the form of separate elements of fuel assemblies and congestions of Fuel Containing Materials.<br />
The de?ontamination works carried out in 1986, have allowed to clean up ChNPP site from a main part of radioactive substances.<br />
That has provided a possibility to operate ChNPP site equipment without the excess of a dose limit established in normative<br />
documents. But a significant amount of reactor core fragments (according to some estimations - from 500 kg up to 1000 kg)<br />
remains at ChNPP territory under a concrete and ground layer, laid in 1986 with the purpose to reduce radiation conditions parameters<br />
at the site up to the normative documents requirements. The given circumstance<br />
2) DIVISION OF NUCLEAR LIABILITIES BETWEEN DIFFERENT LICENSE HOLDERS AND OWNERS (wP-59214)<br />
Staffan Lindskog, Swedísh Radiation Safety Authority; Rolf Sjöblom, Tekedo AB (Sweden)<br />
Operation of nuclear facilities typically implies that substantial liabilities for decommissioning and waste management are<br />
incurred. In the case of Sweden, and in accordance with the polluter pays principle, money is collected into segregated funds and<br />
securities are provided to ensure that adequate funding will be available at the time when it is needed. For nuclear power plants,<br />
the safeguarding of funds includes the estimated costs as well as an amount related to the risk that the Government takes as the ultimate<br />
guardian of the system.<br />
For other license holders, the fees and securities must include only the estimated cost. For old facilities, special problems may<br />
arise since they might no longer generate any revenue. Another problem with old facilities is that it has been proven difficult, in<br />
many cases, to obtain sufficiently precise cost calculations. There issues have been dealt with in previous presentations to the ICEM<br />
by the present authors.<br />
However, equally important - but so far largely neglected - is the issue of who is actually responsible for what. Of course, our<br />
Environmental Code - as does the corresponding legislation in many other countries - states that the responsibility is a collective<br />
one, and anyone involved can…<br />
3) SPANISH APPROACH TO LARGE DECOMMISSIONING PROJECTS (wP-59320)<br />
Juan Santiago, Alejandro Rodríguez, ENRESA (Spain)<br />
Spain has accumulated significant experience in the field of decommissioning of nuclear and radioactive facilities. Relevant<br />
projects include the decommissioning of research reactors and nuclear research facilities and the decommissioning of gas-graphite<br />
and light water nuclear power plants. The decommissioning of nuclear facilities in Spain is undertaken by ENRESA, who is also<br />
responsible for the management of radioactive wastes. The three most notable projects are the decommissioning of the Vandellós I<br />
nuclear power plant, the decommissioning of the CIEMAT Nuclear Research Centre and the decommissioning of the José Cabrera<br />
nuclear power plant.<br />
The Vandellós I gas-graphite reactor was decommissioned in about five years (from 1998 to 2003) to what it is known as level<br />
2. During this period, most plant systems and components were dismantled, the reactor vessel was confined and the facility was<br />
prepared for latency. In 2005 the facility entered into a dormancy phase, with minimum operating requirements.<br />
The decommissioning of the CIEMAT Research Center includes the dismantling of obsolete facilities, such as the research<br />
reactor JEN-1, a pilot reprocessing plant, and a conditioning and storage liquid waste facility and the remediation of contaminated<br />
soils. Dismantling works started in 2006 and have been completed by 2010.<br />
In March…<br />
4) DECOMMISSIONING OF OBSOLETE NUCLEAR FACILITIES IN THE<br />
NUCLEAR RESEARCH INSTITUTE REZ (wP-59309)<br />
Josef Podlaha, Karel Svoboda, Nuclear Research Institute Rez; Eduard Hanslik,<br />
T.G.M. Water Research Institute (Czech Republic)<br />
After more than 55 years of activities of the Nuclear Research Institute Rez (NRI) in the nuclear field, there are some obsolete<br />
nuclear facilities that shall be decommissioned.<br />
NRI is a leading institution in all areas of nuclear R&D in the Czech Republic. NRI has had a dominant position in the nuclear<br />
programme since it was established in 1955 as a state-owned research organization and it has developed to its current status. In<br />
December 1992, NRI has been transformed into a joint-stock company.<br />
The Institute’s activity encompasses nuclear physics, chemistry, nuclear power, experiments at the research reactor and many<br />
other topics. Main issues addressed in NRI in the past decades were concentrated on research, development and services provided<br />
to the nuclear power plants operating VVER reactors, development of chemical technologies for fuel cycle and irradiation services<br />
to research and development in the industrial sector, agriculture, food processing and medicine.<br />
The NRI operates two research nuclear reactors, many facilities as a hot cell facility, research laboratories, technology for<br />
radioactive waste (RAW) management, radionuclide irradiators, an electron accelerator, etc.<br />
The obsolete facilities to be decommissioned comprise:<br />
(1) Various research facilities<br />
Hot cells used for research in the field of reprocessing of…<br />
77
Session 17 Abstracts<br />
SESSION 17 — APPLYING STRATEGIC PLANNING, DECISION-MAKING AND<br />
RISK REDUCTION METHODOLOGIES IN EM (5.7)<br />
1) CAN SUSTAINABILITY BE APPLIED TO OUR ENVIRONMENTAL<br />
REMEDIATION CHALLENGES? (w/oP-59148)<br />
Peter Booth, Vicky Gaskin, WSP Environment and Energy (UK)<br />
There are many environmental remediation challenges around the world today with a radiological connotation. These in turn<br />
relate to all aspects of the nuclear industry life cycle as well as the NORM industries and consequences of accidents /incidents.<br />
In reality, apart from one or two major exceptions in a few counties who have extensive budgets allocated to environmental<br />
remediation, we do not generally see a lot of real progress in the protection of human health and the environment from legacy issues.<br />
It is important therefore to determine why this is the case and if there is anything that can be undertaken to improve the situation.<br />
There are a number of reasons potentially leading to this lack of progress, namely;<br />
• A lack of available funding;<br />
• The diversion of funds to other issues deemed to be a greater priority;<br />
• No practical experience in resolving such problems;<br />
• Lack of established regulatory and/or procedural infrastructure.<br />
More often than not when environmental remediation challenges exist, the decision makers only tend to look for final solutions.<br />
If such final solutions cant be achieved, often because of funding restrictions, then little or no progress is generally made.<br />
However, there is the potential through…<br />
2) EVOLUTION OF PERFORMANCE ASSESSMENT MODELING IN THE US (w/oP- 59334)<br />
Paul Black, John Tauxe, Neptune and Company, Inc. (USA)<br />
Performance Assessment under DOE Orders and NRC regulations are evolving from the deterministic modeling that was performed<br />
in the 1990s, to the probabilistic modeling that is being performed in current PA efforts. This evolution has also seen a change<br />
from bottom-up process modeling to top-down system modeling, which is better suited for probabilistic modeling performed with<br />
the goal of supporting decision analysis. This evolution is presented, with a description of how process modeling can be used effectively<br />
to support system modeling, and how system modeling can be used effectively in a probabilistic environment to support PA<br />
decisions such as disposal optimization, closure, and long-term management and maintenance. The decision analysis process implied<br />
by this approach follows the basic tenets of Bayesian methods, the scientific method, and DOE’s as low as reasonably achievable<br />
process, and allows DOE’s performance assessment maintenance program to become operational and measurable. Technical nuances<br />
in this type of PA modeling such as uncertainty and sensitivity analysis methods that can be applied to such complex, dynamic, nonlinear,<br />
non-monotonic models, and issues associated with proper model scaling are also presented. Specific examples are presented<br />
from performance assessment modeling conducted at several radioactive waste disposal facilities in the US.<br />
SESSION 18 — ECONOMIC ANALYSES, MONITORING STRATEGIES AND PROJECT<br />
MANAGEMENT IN ENVIRONMENTAL MANAGEMENT (5.6)<br />
1) DELIVERING VALUE FOR MONEY - TRUST AND VERIFY? (wP-59253)<br />
Alastair Laird, Project Time & Cost Inc. (USA)<br />
Accurate estimates for national Environmental Management remediation work programmes are an essential ingredient of<br />
ensuring that plans can be adequately funded. They also form the basis of value measurement as the work is executed on an annual<br />
or programme basis. However, the inherent uncertainties of many of the EM and decommissioning tasks, both in terms of the<br />
technical challenges faced, options available, end states to be achieved; and the general risks and uncertainties associated with the<br />
hazard and its characterisation means that many estimates were always going to be subject of very high levels of uncertainty.<br />
In 2002 the United Kingdom Nuclear Liabilities Estimate was quoted as £48Bn when the government restructured the UK civil<br />
nuclear industry and set out the basis for forming what was to become the Nuclear Decommissioning Authority (NDA). By 2005<br />
the NDA had assessed the costs as £56Bn but by 2008 the costs had significantly increased to £73Bn and continue to rise. How<br />
does this relate to the more immediate challenges of working off the plan and demonstrating Value for Money can be achieved in<br />
the near term? In parallel the US Department of Energy EM Office introduced its best-in-class initiative in 2007 – the…<br />
2) THE TECHNICAL AND ECONOMICAL OPTIMIZATION OF THE<br />
FRENCH GEOLOGICAL REPOSITORY PROJECT (w/oP-59275)<br />
Rodolphe Raffard, Thibaud Labalette, Andra (France)<br />
The French Act of 28 June 2006 made the choice of reversible geological repository for long term management of high level<br />
and long-lived intermediate level waste. Andra is in charge of designing, building and operating the future industrial repository<br />
Cigéo. Current major issues consist in preparing the application to be examined in 2015, planning the construction so that operation<br />
would start in 2025 and optimizing the design on both technical and economical points of view.<br />
The Dossier 2005 -provided by Andra prior to the 2006 Act- established the feasibility of the project, especially towards compliance<br />
with safety and reversibility. Design options were presented at that time with the objective of demonstrating feasibility without<br />
ruling out possibilities of further optimization.<br />
Along with the scientific and technical review of Dossier 2005, a number of design optimization topics were identified in 2006.<br />
Working groups involved Andras specialists as well as external experts. A particular attention was given to (i) the industrial experience<br />
of waste producers and (ii) the characteristics of the clay layer investigated in the Meuse/Haute-Marne Underground<br />
Research Laboratory.<br />
The 2006 optimization topics were prioritized taking into account their economical impact and the development plan of the<br />
project. They have been implemented…<br />
78
Abstracts Session 19<br />
3) THE ENVIRONMENTAL MONITORING SYSTEM DEVELOPED WITHIN THE FRAMEWORK<br />
OF THE FRENCH RADIOACTIVE WASTE DEEP REPOSITORY PROJECT (w/oP-59296)<br />
Elisabeth Leclerc; Patrick Landais, Andra (France)<br />
In 2007, an environmental monitoring system, called the Observatoire Pérenne de lEnvironnement (OPE) was launched by<br />
Andra in order to establish the environmental initial state and to monitor ecosystems around the Meuse/Haute-Marne region (East<br />
of France), before the potential installation of a national deep repository of radioactive waste. The OPE aims to characterize an area<br />
covering 900 hundreds of kilometres and to follow environmental evolutions during exploitation, i.e. over 100 years.<br />
The OPE is associated to a comprehensive research and development program involving the deployment of important scientific<br />
tools covering all environmental compartments since several years. The objectives are:<br />
• to gather and analyse physical, chemical, biological and radiological data on the initial state of the environment including<br />
samples preservation from different areas (air, water, forest wildlife and flora, soils, agricultural food chain, etc.)<br />
• to assess the very long term evolution of the environmental quality;<br />
• to model elements biogeochemical cycles, mass and energy fluxes and to study interactions of processes between environmental<br />
areas;<br />
• to anticipate impacts from anthropogenic pressures (industrial, agricultural, climatic, on a local or global scale);<br />
• to study links between environment and human health.<br />
The OPE is currently developing large-scale scientific tools and collecting…<br />
SESSION 19 — POSTER SESSION: SPENT FUEL, FISSILE, TRANSURANIC<br />
AND HIGH LEVEL WASTE MANAGEMENT (2.1)<br />
1) ADONIS, HIGH COUNT RATE HP-GE Ƴ SPECTROMETRY ALGORITHM:<br />
IRRADIATED FUEL ASSEMBLY MEASUREMENT (wP-59234)<br />
Patrick Pin, AREVA NC; Eric Barat, Thomas Dautremer, Thierry Montagu, Stéphane Normand, CEA - Saclay (France)<br />
ADONIS is a digital system for gamma-ray spectrometry, developed by CEA. This system achieves high count-rate gammaray<br />
spectrometry with correct dynamic dead-time correction, up to, at least, more than an incoming count rate of 3:106 events per second.<br />
An application of such a system at AREVA NC’s La Hague plant is the irradiated fuel scanning facility before reprocessing.<br />
The ADONIS system is presented, then the measurement set-up and, last, the measurement results with reference measurements.<br />
2) TECHNICAL KNOW-HOW FOR THE INVESTIGATION AND MODELLING OF<br />
TOPOGRAPHIC EVOLUTION FOR SITE CHARACTERISATION (wP-59171)<br />
Ryosuke Doke, Ken-ichi Yasue, Tadafumi Niizato, Akio Nakayasu, Japan Atomic Energy Agency (Japan)<br />
Geological hazard assessments are being used to make important decisions relevant to the constructing nuclear facilities such<br />
as repositories for deep geological disposal of high-level radioactive waste. With respect to such repositories, topographic evolution<br />
is a key issue for description of the long-term evolution of a groundwater flow characteristics in time spans of tens to hundreds<br />
of thousands of years. The construction of topographic evolution model is complex, involving tacit knowledge and working<br />
processes. Therefore, it is important to externalise, that is to explicitly present the tacit knowledge and decision-making processes<br />
used by experts in the model building unambiguously, with thorough documentation and to provide key knowledge to support planning<br />
and implementation of investigations.<br />
In this study, documentation of the technical know-how used for the construction of a topographic evolution model is demonstrated.<br />
The process followed in the construction of the model is illustrated using task-flow logic diagrams; the process involves<br />
four main tasks with several subtasks. The task-flow for an investigation to estimate uplift rates is also illustrated linked to the taskflow<br />
for the modelling of topographic evolution. In addition, the decision-making processes in the investigation are expressed in<br />
logical IF-THEN format for each task. Based on the documented…<br />
3) VALIDATION OF CORRELATIONS BETWEEN ND ISOTOPES AND DIFFICULT-TO-MEASURE NUCLIDES<br />
PREDICTED WITH BURN-UP CALCULATION CODE BY POST IRRADIATION EXAMINATION (wP-59086)<br />
Shiho Asai, Keisuke Okumura, Yukiko Hanzawa, Hideya Suzuki, Masaaki Toshimitsu, Jun Inagawa, Takaumi Kimura,<br />
Japan Atomic Energy Agency; Satoru Kaneko, Kensuke Suzuki, Tokyo Electric Power Company (Japan)<br />
Correlations between Nd isotopes and difficult-to-measure (DTM) nuclides, such as Se-79, Tc-99, Sn-126, and Cs-135, predicted<br />
using a calculation code have been validated by postirradiation examination (PIE). The calculation was performed with a<br />
burnup calculation code, MVP-BURN, using the updated nuclear data library JENDL-4.0. An irradiated PWR fuel with a burnup<br />
of 44.9 GWd/t and a cooling time of 7458 days was used as a standard sample. The concentrations of Nd isotopes in the sample<br />
solutions were determined by inductively coupled plasma mass spectrometry (ICP-MS) after purification by two consecutive anionexchange<br />
separations. The ratios of Se-79 and Cs-135 to Nd isotopes (Nd-145, Nd-146, and Nd-145+Nd-146) calculated using<br />
MVP-BURN were in good agreement with PIE values within the deviations of 8% and 6%, respectively. This indicates that these<br />
calculated ratios are applicable to the scaling factors of Se-79 and Cs-135. For Tc-99 and Sn-126, the calculated values were respectively<br />
about 50% and 20% higher than the PIE values. These overestimations were mainly caused by the lack of the contribution<br />
of an insoluble residue to the measured concentrations.<br />
79
Session 19 Abstracts<br />
4) COMPUTATIONAL STUDY FOR INVENTORY ESTIMATION OF SE-79, TC-99, SN-126, AND CS-135 IN HIGH-<br />
LEVEL RADIOACTIVE WASTES FROM SPENT NUCLEAR FUELS OF LIGHT WATER REACTORS (wP-59087)<br />
Keisuke Okumura, Shiho Asai, Yukiko Hanzawa, Tsutomu Okamoto, Hideya Suzuki, Masaaki Toshimitsu,<br />
Jun Inagawa, Takaumi Kimura, Japan Atomic Energy Agency; Satoru Kaneko,<br />
Kensuke Suzuki, Tokyo Electric Power Company (Japan)<br />
Inventory estimation of long-lived fission products (LLFPs) in high-level radioactive wastes (HLW) from spent nuclear fuels<br />
of light water reactors is important for a safety assessment of their disposal. In order to develop an inventory estimation method of<br />
difficult-to-measure LLFPs (Se-79, Tc-99, Sn-126, and Cs-135), a parametric study was carried out by using a sophisticated burnup<br />
calculation code and data. In the parametric study, fuel specifications and irradiation conditions are changed in the conceivable<br />
range. The considered parameters are fuel assembly types (PWR / BWR), U-235 enrichment, moderator temperature, void fraction,<br />
power density, and so on. From the calculated results, we clarify the burnup characteristics of the target LLFPs and their possible<br />
ranges of generations. <strong>Final</strong>ly, candidates of the key nuclide are proposed for the scaling factor method of HLW.<br />
5) INDUSTRIAL SCALE HL-LL WASTE CANISTER TRANSFER DEMONSTRATOR (wP-59305)<br />
Pascal Champ, Jacques Bardet, Benjamin Attias, Cegelec (France)<br />
In 2007, Cegelec has been attributed a contract by ANDRA under the ESDRED program (Engineering Studies and Demonstrations<br />
of Repository Designs) financed by 13 organisations across Europe, for the design, manufacturing and trial test of a full scale<br />
industrial demonstrator of HL-LL waste canister transfer system.<br />
Completed in 2009, this project gives a good synthesis of solutions the industry can offer in order to manage HLW transportation<br />
with regard to deep geological disposal.<br />
This paper highlights solutions developed and results achieved with numerous pictures of the actual system.<br />
6) CESAR5.3: AN INDUSTRIAL TOOL FOR IRRADIATED NUCLEAR FUEL<br />
AND WASTE CHARACTERISATION, WITH AN ASSOCIATED QUALIFICATION (w/oP-59080)<br />
Jean-Marc Vidal, Romain Eschbach, Commissariat à lÉnergie Atomique et aux Énergies Alternatives;<br />
Agnes Launay, Christophe Binet, AREVA_NC (France)<br />
CESAR (Simplified Evolution Code Applied to Reprocessing) is a depletion code developed between CEA and AREVA. This<br />
code was first used in the La Hague reprocessing plant Laboratories in 1980, to confirm the nuclear data experimental measurements.<br />
The use of the CESAR code was then extended to the characterizations of various type of irradiated nuclear fuel (PWR/UOx<br />
URE and MOx ; BWR/UOx and MOx ; MTR and Fast Reactors) and the associated produced waste. The code can distinguish more<br />
than 100 heavy nuclides, 200 fission products and 150 activation products (in particular Tritium and Helium generation are included).<br />
Both the fuel and its structural materials can be characterized. The CESAR code can also perform depletion calculations from<br />
3 months to 1 million years of cooling time.<br />
The updated version of the code is related to the harmonization between nuclear data and calculation schemes (APOLLO2)<br />
based on the JEFF3.1.1 nuclear data library. The current features allow fast characterizations for both irradiated fuel and waste, calculating:<br />
material balance, activity, decay heat, neutron source and spectrum, radiotoxicity source, gamma and alpha source and<br />
their respective spectrum. The CESAR code can also calculate the coefficients used in nuclear material transport and in classification<br />
of…<br />
7) TEST PROCEDURE WITH A 15,000 KG HALF-SCALE PROTOTYPE<br />
OF TRANSPORT AND STORAGE CASK (w/oP-59141)<br />
Andre Musolff, Thomas Quercetti,<br />
Karsten Müller, BAM - Federal Institute for Materials Research and Testing (Germany)<br />
BAM is the competent authority for mechanical and thermal safety assessment of transport packages for spent fuel and high<br />
level waste in Germany. In context with the package design approval procedure for transport and storage of new German cask several<br />
drop test series were performed by BAM with a half-scale prototype.<br />
The test program comprised a sequence of a total of 18 drop tests with different drop orientations, drop heights and temperatures.<br />
The sequence of testing in the program consisted of a number of nine-meter free drop onto an unyielding target and several<br />
drops from one meter onto a steel puncture bar. In order to cause maximum damage on the package various drop orientations were<br />
performed according to the most severe drop position as well as most sensitive parts of the container.<br />
The subsequent release of radioactive substances must not exceed a value specified in the dangerous goods transport regulations.<br />
Radiation shielding and nuclear safety has to be guaranteed. The prototype was tested under normal and accident conditions<br />
of transport in the 200 tons BAM drop test facility at BAM Test Site Technical Safety.<br />
Extensive test methods as well as comprehensive measurement data are presented within the complexity of performed drop test<br />
procedures.<br />
8) CAPILLARY ELECTROPHORESIS WITH LASER-INDUCED FLUORESCENT DETECTION METHOD USING<br />
HIGHLY EMISSIVE PROBES FOR ANALYSIS OF ACTINIDES IN RADIOACTIVE WASTES (wP-59092)<br />
Tomoko Haraga, Japan Atomic Energy Agency; Yuta Nakano, Masami Shibukawa, Saitama University; Yutaka Kameo,<br />
Kuniaki Takahashi, Japan Atomic Energy Agency; Shingo Saito, Saitama University (Japan)<br />
For the safe disposal of radioactive wastes, it is indispensable to evaluate radioactivity concentration in each waste package.<br />
Actinides are important nuclides for the safety analysis of radioactive wastes from nuclear fuel cycle facilities. In order to analyze<br />
many kinds of waste samples, a simple, fast and highly sensitive analytical method for actinides is required. While capillary electrophoresis<br />
(CE) has been employed for the analysis of ionic species including actinide ions with advantage of the high separation<br />
efficiency and simpleness so far, there is no report for CE method providing high sensitivity amenable to practical use, to our<br />
knowledge. In this study, an approach to develop new emissive probes for actinide ions using CE-laser-induced fluorescent detection<br />
(LIF) was made for the first time. The separation and detection of neptunium (Np-237) and americium (Am-243) was exam-<br />
80
Abstracts Session 19<br />
ined as a model nuclide using several new emissive complexing probes, each of which possesses a fluorophore (fluorescein) and a<br />
different chelating moiety (hexa-octadentate, and acyclic or macrocyclic polyaminocarboxylate). Applying the actinide-probe complexes<br />
to a pre-capillary complexation technique, in which an emissive probe was mixed to a sample solution before electrophoresis<br />
without addition of the emissive probe to the carrier electrolyte, the highly sensitive fluorescent detection…<br />
9) A NEW WAY OF ELIMINATING TRIBUTYLPHOSPHATE AND DODECANE MIXTURES<br />
USING ADVANCED OXIDATION TECHNIQUES (w/oP-59104)<br />
Geraldine Dupuy, DEWDROPS (France)<br />
Tributylphosphate (TBP)/dodecane mixtures are widely used as extraction solvents in the PUREX process. The process is well<br />
known as an efficient method for Uranium and Plutonium recovery from spent nuclear fuel. After undergoing several cycles, the<br />
performance of the PUREX process is impaired by chemical and radiolytic damage to the TBP and dodecane molecules. The used<br />
extraction solvent becomes an organic nuclear waste for which disposal options are scarce. Currently, the dodecane can be recycled<br />
or incinerated after TBP removal to limit corrosion problems. However, the separation of the two solvents still leaves untreated<br />
extraction products that accumulate awaiting a satisfactory disposal solution.<br />
Dewdrops has developed and optimized a treatment based on advanced oxidation techniques that provides an elegant and costeffective<br />
solution particularly well adapted to small arisings of complex mixtures originating from the PUREX process. The organic<br />
waste is completely mineralized yielding only effluents for which disposal routes are already available. The patented oxidation<br />
process uses the combination of hydrogen peroxide and UV-C radiation with or without a catalyst to produce hydroxyl radicals<br />
capable of mineralizing organic matter to carbon dioxide and water. The performance of the process has been proven in an experimental<br />
set up comprising a 14…<br />
10) THE FP7 COLLABORATIVE PROJECT RECOSY (w/oP-59397)<br />
Gunnar Buckau, Institute for Transuranium Elements, Joint Research Center, European Union;<br />
Anne Delos, Vanessa Montoya, Amphos 21 (Germany/France/Spain)<br />
The Collaborative Project REdox phenomena Controlling SYstems (RECOSY) started in 2008 falls within the EURATOM<br />
program and is implemented within the 7th Framework <strong>Program</strong>.<br />
The main objective of ReCosy is the sound understanding of redox phenomena controlling the long-term release/retention of<br />
radionuclides in nuclear waste disposal providing tools to apply the results to Performance Assessment/Safety Case.<br />
Although redox is not a new issue, different questions are still not resolved, such as, redox processes in the long-term dissolution/chemical<br />
transformation of the radioactive waste, waste packages and engineered barriers, and migration in the far-field,<br />
including which species are formed and their respective various retention mechanisms. In order to solve this questions, the project<br />
includes i) development of advanced analytical tools, ii) investigations of processes responsible for redox control (thermodynamically<br />
and kinetically controlled processes, surface reactions and microbial processes), iii) provision of required data on redox controlling<br />
processes, and iv) response to internal/external disturbances in disposal systems to internal/external disturbances.<br />
The work program of the project is structured along six Research and Technological Development workpackages. Specific<br />
workpackages on knowledge management, education and training (WP7) and administrative management issues (WP8) are also<br />
included in the project. In WP1, the scientific state-of-the-art and its application to Performance Assessment/Safety Case is documented<br />
and regularly up-dated, based on the safety case of the ANDRA B2 cell. WP2 deals with the development and testing of<br />
redox determination methods using different type of electrodes as well…<br />
11) TECHNICAL KNOW-HOW OF SITE DESCRIPTIVE MODELING FOR SITE CHARACTERIZATION (wP-59089)<br />
Hiromitsu Saegusa, Tadafumi Niizato, Ken-ichi Yasue, Hironori Onoe,<br />
Ryosuke Doke, Japan Atomic Energy Agency (Japan)<br />
The site descriptive model covering the current status of characteristics of geological environment and the site evolution model<br />
for estimation of the long-term evolution of site conditions are used to integrate multi-disciplinary investigation results. It is important<br />
to evaluate uncertainties in the models, to specify issues regarding the uncertainties and to prioritize the resolution of specified<br />
issues, for the planning of site characterization.<br />
There is a large quantity of technical know-how in the modeling process. It is important to record the technical know-how with<br />
transparency and traceability, since site characterization projects generally need long duration. The transfer of the technical knowhow<br />
accumulated in the research and development (R&D) phase to the implementation phase is equally important.<br />
The aim of this study is to support the planning of initial surface-based site characterizations based on the technical know-how<br />
accumulated from the underground research laboratory projects. These projects are broad scientific studies of the deep geological<br />
environment and provide a technical basis for the geological disposal of high-level radioactive wastes. In this study, a comprehensive<br />
task flow from acquisition of existing data to planning of field investigations through the modeling has been specified. Specific<br />
task flow and decision-making process to perform the tasks have been specified.<br />
81
Session 20 Abstracts<br />
12) A COMPREHENSIVE INFORMATION MANAGEMENT SYSTEM FOR EUROPEAN DISPOSAL R&D<br />
(INMAN): A PROPOSAL FOR THE NEXT EUROPEAN FRAMEWORK PROGRAM (w/oP-59397)<br />
Gunnar Buckau, Institute for Transuranium Elements, Joint Research Center, European Union;<br />
Anne Delos, Vanessa Montoya, Amphos 21 (Germany/France/Spain)<br />
ABSTRACT NOT AVAILABLE<br />
13) DEVELOPMENT OF COMPREHENSIVE TECHNIQUES FOR COASTAL SITE<br />
CHARACTERIZATION: INTEGRATED PALAEOHYDROGEOLOGICAL APPROACH<br />
FOR DEVELOPMENT OF SITE EVOLUTION MODELS (wP-59259)<br />
Kenji Amano, Tadafumi Niizato, Kunio Ota, Japan Atomic Energy Agency; Bill Lanyon, Nagra;<br />
W Russell Alexander, Bedrock Geosciences (Japan/Switzerland)<br />
Radioactive waste repository designs consist of multiple safety barriers which include the waste form, the canister, the engineered<br />
barriers and the geosphere. In many waste programmes, it is considered that the three most important safety features provided<br />
by the geosphere are mechanical stability, favourable geochemical conditions and low groundwater flux. To guarantee that a<br />
repository site will provide such conditions for timescales of relevance to the safety assessment, any repository site characterisation<br />
has to not only define whether these features will function appropriately today, but also to assess if they will remain adequate<br />
up to several thousand to hundreds of thousand years into the future, depending on the repository type.<br />
In general, this is done by studying the palaeohydrogeological evolution of a site, defining the temporal and spatial changes of<br />
various properties and processes. These may include geology, hydrogeology, hydrochemistry and site tectonics, including uplift and<br />
erosion processes. These key aspects are studied to build up a conceptual model for the overall site evolution over geological time,<br />
up to the present and this is used to define the likely future evolution of the site and to assess if the main safety features will continue<br />
to function adequately.<br />
The collaborative programme…<br />
SESSION 20 — PANEL: CHALLENGES WHEN SELECTING DISPOSAL OPTIONS IN THE LIGHT<br />
OF THE NEW IAEA CLASSIFICATION SCHEME (1.17)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 21 — PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF INTERIM STORAGE,<br />
GEOLOGICAL DISPOSAL, PARTITIONING & TRANSMUTATION REVERSIBILITY REGARDING<br />
GLOBAL OPTIMIZATION OF RADWASTE MANAGEMENT (2.15)<br />
NEW NUCLEAR PROGRAMMES MUST NOT NEGLECT WASTE MANAGEMENT (wP-59077)<br />
Charles McCombie, Arius Association (Switzerland)<br />
Many established nuclear power programmes have learned to their dismay that waste management and disposal are not tasks<br />
that can be postponed at will if public and political acceptance is a prerequisite for progress. In fact, some programmes that recognised<br />
this back in the 1970s and 1980s moved into leading positions in repository development. This happened, for example, in<br />
Sweden and Switzerland where already in the 1970s Laws were passed specifying that safe disposal must be demonstarted before<br />
new nuclear plants could opersate. In recent years, it has become recognised that, in order to ensure that the radioactive wastes in<br />
any country are managed safely, it is necessary to have an established legislative and regulatory framework and also to create the<br />
necessary organizations for implementation and for oversight of waste management operations and facility development. Guidance<br />
on these issues is given in the Joint Convention and a number of other IAEA documents. The IAEA, and also the EC, have in addition<br />
published key overarching advisory documents for new nuclear programmes. These are useful for strategic planning but, when<br />
it comes to actual implementation projects, the advice tends to imply that all nuclear programmes, however large or small, should<br />
be pressing…<br />
SESSION 22 — PANEL: CONTRIBUTION AND COMPLEMENTARITIES OF INTERIM STORAGE,<br />
GEOLOGICAL DISPOSAL, PARTITIONING & TRANSMUTATION REVERSIBILITY REGARDING<br />
GLOBAL OPTIMIZATION OF RADWASTE MANAGEMENT (2.15)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 23 — ADVANCED L/ILW CONDITIONING TECHNOLOGIES - PART 1 OF 2 (1.11)<br />
1) CEMENTITIOUS MATERIALS FOR RADIOACTIVE WASTE MANAGEMENT<br />
WITHIN IAEA COORDINATED RESEARCH PROJECT (wP-59021)<br />
Zoran Drace, IAEA; Michael Ojovan, University of Sheffield (Austria/UK)<br />
The IAEA Coordinated Research Project (CRP) on cementitious materials for radioactive waste management was launched in<br />
2007. The objective of CRP was to investigate the behaviour and performance of cementitious materials used in radioactive waste<br />
management system with various purposes and included waste packages, wasteforms and backfills as well as investigation of interactions<br />
and interdependencies of these individual elements during long term storage and disposal. The specific research topics considered<br />
were: (i) cementitious materials for radioactive waste packaging: including radioactive waste immobilization into a solid<br />
waste form, (ii) waste backfilling and containers; (iii) emerging and alternative cementitious systems; (iv) physical-chemical<br />
processes occurring during the hydration and ageing of cement matrices and their influence on the cement matrix quality; (v) methods<br />
of production of cementitious materials for: immobilization into wasteform, backfills and containers; (vi) conditions envisaged<br />
82
Abstracts Session 24<br />
in the disposal environment for packages (physical and chemical conditions, temperature variations, groundwater, radiation fields);<br />
(vii) testing and non-destructive monitoring techniques for quality assurance of cementitious materials; (viii) waste acceptance criteria<br />
for waste packages, waste forms and backfills; transport, long term storage and disposal requirements; and finally (ix) modelling<br />
or simulation of long term behaviours of cementations materials used for packaging, waste immobilization and backfilling,…<br />
2) ELUTION BEHAVIOR OF HEAVY METALS FROM CEMENT SOLIDIFIED PRODUCTS<br />
OF INCINERATED ASH WASTE (wP-59102)<br />
Yoshihiro Meguro, Yoshimi Kawato, Takuya Nakayama,Osamu Tomioka,<br />
Motoyuki Mitsuda, Japan Atomic Energy Agency (Japan)<br />
Combustible radioactive wastes generated from the operation of nuclear facilities are incinerated for volume reduction in<br />
Japan. In Japan Atomic Energy Agency (JAEA) the incinerated ash is planned to be solidified using cement and to be buried in the<br />
ground. Incinerated ashes with various compositions and properties are generated because there are facilities of several kinds of<br />
types such as reactors, nuclear fuel cycle facilities, and hot laboratories in JAEA. And also a small amount of heavy metal, which<br />
is hazardous chemical substance for environment, is also included in the incinerated ash.<br />
The authors push forward a study to determine conditions to produce solidified products of the incinerated ash with cement.<br />
Here relationships between solidification conditions and solidification characteristics have been investigated. The solidification<br />
conditions are the ash composition, cement materials, ash filling rate and water/cement ratio, and the solidification characteristics<br />
are including curing rate and expansion behavior. And also characteristics of the solidified product have been studied, these are<br />
compressive strength, elution behavior of radionuclides and the heavy metals from the solidified products, gas generation by radiolysis,<br />
and so on.<br />
In the present paper, our recent results about the elution behavior of the hazardous heavy metals from synthetic solidified…<br />
3)IMMOBILISATION OF RADWASTE IN SYNTHETIC ROCK: AN ALTERNATIVE TO CEMENTATION (w/P-59008)<br />
Bernard Rottner, Onet Technologies (France)<br />
SOGETER is a waste conditioning process for Low Level radwaste (LLW) or Intermediate Level radwaste (ILW) like sludge,<br />
soil, ashes, evaporator concentrate, concrete rubble, asbestos, sand, & Usually such radioactive waste is solidified into a cement<br />
matrix, resulting in a factor 2 to 5 volume increase: 1 m3 of initial raw waste generates 2 to 5 m3 of solidified waste.<br />
Sogeter consists in melting the waste at high temperature, up to 2000 K, and producing a synthetic rock. The main component<br />
of the matrix is the waste itself; therefore 1 m3 of initial raw waste generates only 0.2 to 0.5 m3 of solidified waste.<br />
Compared to cementation, synthetic rock decreases the volume to be disposed of by a factor of 4 to 25.<br />
By mixing different types of waste, or using additives, the composition of the waste is adjusted, so that a fluid melt is obtained<br />
at temperatures less than 2000 K, and so that the final 200 L ingot may be cooled down within 2 days, without shattering or disaggregating.<br />
We tested a wide range of compositions, demonstrating that almost every type of waste may be conditioned with Sogeter.<br />
We designed the industrial facility, based on a very robust and…<br />
SESSION 24 — L/ILW WASTE CHARACTERIZATION, ASSAY, AND TRACKING SYSTEMS - PART 1 OF 2 (1.7)<br />
1) A PROPOSED FIGURE OF MERIT FOR EVALUATING THE PERFORMANCE<br />
OF RADIATION IDENTIFICATION AND DETECTION SYSTEMS (wP-59159)<br />
Ronald Keyser, Timothy Twomey, ORTEC - AMETEK; Michael D. Belbot, Thermo Fisher Scientific;<br />
Neil Andrew Webster, Thermo Fisher Scientific, Radiation Measurement & Security Instruments (USA)<br />
The instruments used to monitor the radioactive content of waste materials, either in container monitors, hand held radiation<br />
detectors, or mobile analysis systems, are constructed of widely different ways with widely varying detector materials and analysis<br />
software. However, within the various groupings (e.g., automatic waste monitors), all instruments are expected to solve the same<br />
problem, that is, to detect and identify any radioactive material present according to the prescribed investigation methods. The best<br />
way to compare the performance of different instruments is with a numerical score or Figure of Merit (FOM). The FOM must quantity<br />
the performance of the instrument with respect to false positives (FP) and false negatives (FN). The minimization of FN for<br />
certain radionuclides (e.g., uranium and plutonium or SNM) is more important than the minimization of FN for non-threat nuclides<br />
(e.g., low NORM). Likewise, the minimization of FP for SNM is also more important than falsely reporting the common NORM<br />
nuclides. The performance depends on the details of the testing, so the analysis conditions must also be included in the statement<br />
of the FOM. A FOM has been developed based on the number of true positives (TP), the number of false important positives (FIP),<br />
the number…<br />
2) CHARACTERIZATION OF LEGACY LOW LEVEL WASTE AT THE SVAFO<br />
FACILITY USING GAMMA NON-DESTRUCTIVE ASSAY AND X-RAY<br />
NON-DESTRUCTIVE EXAMINATION TECHNIQUES (wP-59289)<br />
Stephen Halliwell, VJ Technologies Inc;<br />
Gary Mottershead, VJ Technologies Inc; Fredrik Ekenborg (USA/France/Sweden)<br />
Over 7000 drums containing legacy, low level radioactive waste are stored at four SVAFO facilities on the Studsvik site which<br />
is located near Nyköping, Sweden. The vast majority of the waste drums (>6000) were produced between 1969 and 1979. The<br />
remainder were produced from 1980 onwards.<br />
Characterization of the waste was achieved using a combination of non-destructive techniques via mobile equipment located<br />
in the AU building at the Studsvik site. Each drum was weighed and a dose rate measurement was recorded. Gamma spectroscopy<br />
was used to measure and estimate radionuclide content. Real time xray examination was performed to identify such prohibited<br />
items as free liquids.<br />
83
Session 24 Abstracts<br />
3) CALIBRATION AND VALIDATION OF A WIDE RANGE SEGMENTED GAMMA RAY SCANNING<br />
INSTRUMENTS FOR THE MEASUREMENT OF LOW AND INTERMEDIATE LEVEL WASTE (wP-59304)<br />
John Mason, A. N. Technology Ltd.;<br />
Kapila Fernando, ANSTO, Australia Nuclear Science and Technology Organization (UK/Australia)<br />
This paper describes the design and operation of a Wide Range Segmented Gamma ray Scanning (WR-SGS) assay instrument<br />
for the measurement of both Low and Intermediate Level Waste (LLW and ILW) in 200 liter drums. The instrument employs a single<br />
shielded and collimated high purity germanium (HPGe) detector to quantify the radionuclide content of the waste. A novel feature<br />
of the instrument is the use of an automated variable aperture collimator, which allows the vertical segment height to be adjusted.<br />
Conventional SGS measurements may be performed where the drum is rotated and measured in vertical segments. Alternatively,<br />
faster measurement can be made using continuous helical scanning of the drum as it rotates. Intermediate level waste drums,<br />
with significant surface dose rates, can be measured through the use of the variable aperture collimator. A gamma ray emitting transmission<br />
source is used to correct for waste density. In place of a conventional shutter, the shielded transmission source is moved to<br />
a shielded storage position to eliminate background radiation arising from the transmission source. Using this approach, higher<br />
activity transmission sources may be used in order to achieve adequate density corrections for higher density drums.<br />
These new features makes the WR-SGS suitable for…<br />
4) PERFORMANCE OF A DRUMSCAN® HRGS SOLO SCANNER FOR THE ASSAY<br />
OF LEGACY WASTE AT THE BELGOPROCESS SITE (wP-59122)<br />
Daniel Parvin, Babcock International Group; Thomas Huys, Belgoprocess, Dessel, (UK/Belgium)<br />
On the sites of Belgoprocess several thousands of drums containing conditioned legacy waste are stored. A significant number<br />
of these waste packages are 220 litre drums containing radioactive waste embedded into inactive bitumen. Most of the radioactive<br />
waste in these drums was generated during the development and production of MOX-fuels and the operation of the Eurochemic<br />
reprocessing plant. The current state of a number of these packages is no longer acceptable for long term interim storage. In order<br />
to make the waste packages acceptable for interim storage a repackaging process was developed. The process involves the re-packaging<br />
of the waste items into 400 or 700 litre waste drums and a non-destructive gamma-ray assay (NDA) measurement performed<br />
on the new package. The aim of the NDA measurement is to detect significant quantities of fissile material in order to demonstrate<br />
compliance with the operational limits of the storage building. Since the waste items are destined for geological disposal, there is<br />
no specific need for a detection limit in the order of milligrams of plutonium as required for surface disposal.<br />
To meet this NDA requirement Babcock International Group supplied, calibrated and commissioned an open geometry version<br />
from its HRGS product range. The DrumScan®…<br />
SESSION 25 — D&D OF NON-REACTOR NUCLEAR FACILITIES (3.10)<br />
1) DECOMMISSIONING THE BELGONUCLEAIRE DESSEL MOX PLANT: PRESENTATION<br />
OF THE PROJECT AND SITUATION ON 30/06/2011 (wP-59027)<br />
Jean-Marie Cuchet, Carlo Verheyen, Henri Libon, Belgonucleaire; Jos Custers, Tecnubel; Robert Walthery,<br />
Belgoprocess; Jozef Bily, Studsvik (Germany)<br />
BELGONUCLEAIRE has been operating the Dessel MOX plant at industrial scale between 1986 and 2006. In this period, 40<br />
metric tons of plutonium (HM) have been processed into 90 reloads of MOX fuel for commercial light water reactors. The decision<br />
to stop the production in 2006 and to decommission the MOX plant was the result of the shrinkage of the MOX fuel market<br />
owing to political and customers factors.<br />
As a significant part of the decommissioning project of the Dessel MOX plant, about 170 medium-sized glove boxes and about<br />
1.300 metric tons of structure and equipment outside the glove boxes are planned for dismantling.<br />
The license for the dismantling of the MOX plant was granted by Royal Decree in 2008 and the dismantling started in March<br />
2009; the dismantling works are executed by an integrated organization under leadership and responsibility of BELGONUCLE-<br />
AIRE with 3 main contractors, namely Tecnubel N.V., the THV Belgoprocess / SCK•CEN and Studsvik GmbH<br />
In this paper, after having described the main characteristics of the project, the authors introduce the different organisational<br />
and technical options considered for the decommissioning of the glove boxes, and the main decision criteria (qualification of personnel<br />
and of processes, confinement, cutting techniques…<br />
2) URANIUM WORKSHOPS DISMANTLING AND CRITICALITY CONTROL (wP-59060)<br />
Pierre Lisbonne, Julie Rosello, CEA (France)<br />
Within the CEA at Cadarache Research Center located in southern France, the ATUE, standing for Ateliers de Traitement de<br />
lUranium Enrichi (Enriched Uranium Treatment Workshops), is a nuclear facility started in 1965, and shut down in 1995.<br />
Various chemical processes were in operation in the ATUE in order to product enriched uranium oxide intended for fast breeders<br />
and naval propulsion reactors.<br />
According to the mass of fissile material, the most contaminated process equipment has already been dismantled under criticality<br />
risk management procedures. Cleanup of the building and dismantling of the remaining equipment, such as ventilation and<br />
electricity network, are now in progress without any constraint regarding criticality, thanks to in site measurement and calculations.<br />
Criticality management and how we finally proved the risk was over, as well as the strategy under French rules for final decommissioning<br />
of the facility leading to brown field will be presented.<br />
84
Abstracts Session 25<br />
3) THE COMPLEX CHALLENGE OF REFURBISHING THE POND GANTRY STEELWORK<br />
WHICH SUPPORTS THE POND SKIP HANDLER ABOVE THE FIRST GENERATION<br />
MAGNOX STORAGE POND AT SELLAFIELD (wP-59133)<br />
Ian Richardson, Sellafield (UK)<br />
The First Generation Magnox Fuel Storage Pond (FGMSP) provided fuel storage and decanning capability from the early<br />
1960s until 1986.<br />
A significant programme of work has been underway since the completion of operational activities to support the programmes<br />
strategic intent of retrieving and storing all legacy wastes, and remediating the structure of the plant to support decommissioning<br />
activities.<br />
A key enabler to the retrievals programme is the Pond Skip Handler Machine (SHM), removed from service in 2002 following<br />
the discovery of significant signs of corrosion, an inevitable consequence of being located in a coastal, salt laden environment.<br />
The SHM provides sole capability to access and retrieve the inventory of the fuel skips in the pond. It is also fundamental to<br />
future operations and the deployment of desludging equipment to recover bulk sludges from the pond floor.<br />
This paper will examine the challenges faced by the team as they successfully defined, planned and executed remedial work<br />
to a specific aspect of the civil structure, the SHM gantry rail system, using a purpose built refurbishment platform; the Gantry<br />
Refurbishment System.<br />
The paper will examine how an innovative approach was adopted to resolve the related issues of:<br />
• Refurbishing an aged structure to….<br />
4) SYSTEMATIC CHEMICAL DECONTAMINATION USING IF7 GAS (wP-59036)<br />
Haruhi Hata, Kaoru Yokoyama, Noritake Sugitsue, Japan Atomic Energy Agency (Japan)<br />
Since 1979, Uranium enrichment technology has been researched through the gas centrifuge method, at Ningyo-toge Environmental<br />
Engineering Center of Japan Atomic Energy Agency(JAEA). In addition, the Demonstration Plant, that is final stage test<br />
facilities, was operating continuously from 1988 to 2001.<br />
As a result, a lot of residues accumulated in the plant. Most of this accumulation was found be uranium intermediate fluoride.<br />
The basic decommission policy of JAEA is that equipments of gas centrifuge will be decontaminated by sulfuric acid immersion<br />
method for clearance and reuse.<br />
In our plan, approximately 90% of metals will be cleared and reused, and then the remaining 10% will be disposed of radioactive<br />
waste.<br />
We propose a combination of sulfuric acid immersion method and the systematic chemical decontamination as an efficient<br />
method for decontamination of uranium enrichment facilities. This paper focuses on the method and performance of systematic<br />
chemical decontamination using IF7gas. The following (Figure 1)shows our decommission policy and position of systematic chemical<br />
decontamination by IF7gas for uranium enrichment plant...<br />
5) DECOMMISSIONING & DEMOLITION OF FACILITIES USED FOR THE STORAGE<br />
& STABILISATION OF WATER REACTOR SLUDGE (wP-59097)<br />
Nicholas J. Brown, Rowland Cornell, Nuvia Limited; Andy Staples, RSRL (UK)<br />
Nuvia Limited was contracted to design, build and operate a waste treatment plant to stabilise a quantity of about 300m3 of<br />
active sludge stored in the External Active Storage Tanks (EAST) at the former United Kingdom Atomic Energy Authority<br />
(UKAEA) research site at Winfrith, UK. At the end of this process both the old and new plants are to be decommissioned and<br />
demolished with the minimisation of waste material volumes. The sludge was produced in the Steam Generating Heavy Water<br />
Reactor (SGHWR) during 30 years of operation, which is now in the early stages of decommissioning. As part of the reorganisation<br />
of UKAEA responsibility for the site now lies with RSRL (Research Sites Restoration Limited) with funding provided by the<br />
Nuclear Decommissioning Authority (NDA).<br />
The process of stabilisation of the SGHWR sludge from the EAST tanks within 500 litre stainless steel drums in the newly<br />
constructed Winfrith EAST Treatment Plant (WETP) was completed in March 2010. Now that these operations have been completed,<br />
the plant has entered a full decommissioning phase since no further work on any other waste materials have been identified by<br />
the client.<br />
This paper describes the development of a decommissioning plan for the mixture of old…<br />
6) DECOMMISSIONING OF THE RADIO CHEMICAL HOT LABORATORY OF THE<br />
EUROPEAN COMMISSION JOINT RESEARCH CENTRE OF ISPRA (wP-59207)<br />
Daniele Ugolini, Francesco Rossi, Francesco Basile, European Commission Joint Research Centre (Italy)<br />
The construction of the Radio Chemical Hot Laboratory (RCHL) of the Joint Research Centre (JRC) of Ispra began in the early<br />
1960s while the laboratory activities started in 1964. In 1976 an annex to the main building was built. At this time the RCHL main<br />
research activities were in environment and biochemistry by means of radioactive tracers; neutron activation analyses; extraction<br />
of actinides from radioactive liquid waste coming from the nuclear fuel reprocessing plants; and analyses of U, Pu, and Th in samples<br />
from the nuclear fuel cycle in order to determine the isotopic ratio and the burn-up. In 1978, a new area of laboratories named<br />
Stabularium was built to study the metabolism of heavy metal on laboratory animals. Complementary to the laboratory three pneumatic<br />
transfer systems for irradiated sources connected the RCHL to two research reactors.<br />
The decommissioning activities of the 2650 m2 facility started in January 2008 and they were completed at the end of 2010<br />
with the release for unrestricted use of all the buildings of the facility. They consisted in five main tasks: pre-decommissioning,<br />
licensing, dismantling, waste management, and final survey. The main pre-decommissioning activities were the physical and radiological<br />
characterization of the facility. The principal…<br />
85
Session 26 Abstracts<br />
7) A SUCCESSFUL TRANSITION FROM OPERATING TO DISMANTLING<br />
A UO2-PUO2 FUEL FABRICATION FACILITY (w/oP-59326)<br />
Thierry Flament, AREVA NC (France)<br />
After fabricating plutonium fuels for 40 years (Fast bredder reactor, Mox), commercial operations at the AREVA Cadarache<br />
plant ended in 2003 and post operation clean out of its production building and laboratory started. AREVAs objective is to achieve<br />
the clean-up of the process facilities and to transfer them to their owner, the French Atomic Energy Commission. The completion<br />
of this operation demonstrates the possibility to dismantle plutonium fuel fabrication facility and the possibility to reuse the facilities.<br />
The facilities to be dismantled by AREVA at Cadarache include:<br />
About 420 glove boxes containing various types of equipment (process equipment for nuclear fuel fabrication, analytical equipment<br />
to characterize fabricated fuel, process equipment to recover valuable materials (Uranium and plutonium) and calcine liquid<br />
effluent),<br />
• About 40 storage tanks<br />
• 3 major steps in this large D&D programme<br />
• Recovery of fissile materials left in the facility led by a project team:<br />
• 25 metric tons of mixed oxide materials in the various glove boxes / storage were recovered in less than 5 years...<br />
SESSION 26 — D&D TECHNOLOGIES - PART 1 OF 2 (3.4)<br />
1) DISMANTLING/REMEDIATION OF A HIGHLY CONTAMINATED SUMP<br />
IN RUNNING PLANT CONDITIONS (w/oP-59053)<br />
Jos Boussu, Koen Lenie, Tecnubel (Belgium)<br />
A sump in the RPE circuit in the EDF - Nuclear Power Plant of Cruas-Meysse, showed a extremely high radiation dose rate<br />
since 2007.<br />
Different attempts to decontaminate the sump did not have the desired effect.<br />
The sump is a so-called gatte where two flows of different fluida circulates. A chemical flow transverses the sump within stainless<br />
steel piping, the second flow which is (contaminated) residual water, flows through this sump in contact with the sumps walls.<br />
The dose rate was estimated at 20 Sv/h, and it was presumed being a single hotspot in the dead zone of the sump, where no<br />
chemicals from the chemical decontamination attempts, and no high pressure water contact had been possible, or had any effect.<br />
To protect the maintenance and exploitation people from the radiation, the sump had been protected with a physical protection<br />
system, named a sarcophage. The client asked to leave this protection system, which was modular, on place during the dismantling<br />
works to assure its radiation protection function.<br />
The paper describes the remote controlled dismantling of the sump within the particular running conditions of the power plant,<br />
the developments made to the equipment, and the conditions in which the works had to be carried out.<br />
Some lessons learnt and particular points of attention are revealed to complete this paper.<br />
2) NEW DEGREASING FORMULATIONS FOR THE DECONTAMINATION OF SOLID SUBSTRATES,<br />
CONSISTENT WITH VITRIFICATION PROCESS OF THE FINAL WASTES (w/oP-59166)<br />
Jeremy Causse, Cyril Roussignol, French Atomic Enrgy Commission; Jean-François<br />
Valery, Jean Charles Hamel, Areva NC (France)<br />
Decontamination shops use various techniques to decontaminate solid substrates. The aim of these shops is either to recover<br />
the substrate for a future second life, or to sufficiently lower the radioactivity level in order to reduce the final waste volume. One<br />
of these techniques remains in aqueous bathes possibly under ultrasonic agitation. This technique is very fit to small metallic pieces.<br />
Most of those pieces are covered with various greases or organic oils very resistant to classical aqueous washes. Thus, this oily<br />
layer contains some unfixed radionuclides that must be removed to reach the decontamination factor targeted. This urged decontamination<br />
shops operating staff to consider additive molecules necessary to render aqueous washes consistent with such a contamination.<br />
These molecules, namely surfactants, act on the liquid surface to increase affinity between aqueous and oily phases.<br />
The surfactant formulations used in French decontamination shops are industrial formulations. Those formulations are generally<br />
designed by international manufacturers to be consistent with several applications. Thus, there isnt any specific formulation fitted<br />
to nuclear applications. But, this way of working is no longer possible now. This is due to the changes of final wastes conditioning<br />
matrix. Indeed, bitumen matrix is devoted to disappear in the next…<br />
3) THE ORION SCANSORT SOIL SORTING SYSTEM (w/oP-59385)<br />
Jeffrey Lively, MACTEC (USA)<br />
Radiologically contaminated sites undergoing remediation or decommissioning typically have large volumes of soil which are<br />
heterogeneously contaminated by radioactivity from historic operations. There is a severe shortage of available disposal space for<br />
this type of material worldwide. It is, therefore, important that volumes being disposed are minimized as far as possible to ensure<br />
efficient use of scarcely available radioactive waste disposal facilities. There are also significant cost savings to be realized from<br />
segregating clean and exempt material from material classified as low-level (radioactive) waste (LLW) for disposal in other (nonradioactive)<br />
facilities or preferably for recycling onsite as part of the site closure process.<br />
The use of a proven dynamic measurement and soil sorting technology has the potential to speed up site closure, reduce LLW<br />
volumes, and save the decommissioning programs significant costs. Conveyor-based, radiological soil measurement systems developed<br />
have been used to process bulk soils with the potential to be contaminated with radioactivity, segregating soils that exceed the<br />
accepted regulatory limits from those that could be reused onsite or otherwise disposed in non-radioactive disposal facilities. This<br />
paper will describe the operation and advanced capabilities of MACTECs state-of-the-science bulk soil survey and sorting system<br />
developed and successfully used in the USA…<br />
86
Abstracts Session 26<br />
4) LIQUIDS, GELS, FOAMS AND SUPERCRITICAL FLUIDS: FOUR STATES OF MATTER<br />
FOR RADIOACTIVE DECONTAMINATION OF SOLIDS (w/oP-59158)<br />
Sylvain Faure, Jérémy Causse, Bruno Fournel, CEA (France)<br />
To face the future challenges in the nuclear industry as dismantling and decommissioning, the Advanced Decontamination<br />
Processes Laboratory (Laboratoire des Procédés Avancés de Décontamination - LPAD) from the French Atomic Energy Commission<br />
(CEA) is developing new radioactive decontamination of solids processes to protect workers and to reduce strongly the quantity<br />
of secondary wastes produced. We have focused in the last past years on the use of four states of matter to develop new patented<br />
nuclear decontamination processes: micellar aqueous solutions, gels, foams and supercritical fluids.<br />
The conference gives an overview of these four ways to decontaminate a solid surface. The major applications and results<br />
obtained on real decontamination operations will be presented for each process. First, micellar solutions based on copolymers<br />
blocks surfactants are presented for radioactive degreasing. The advantage to formulate self-drying and cracking gels films sprayed<br />
on metallic surfaces is then detailed. For decontamination foams, an approach using new additives polymers or particles- is<br />
defended to obtain high life time foams that are able to treat huge and complex shape materials such as fission products tanks or<br />
steam generator. At the end, original works to treat textiles or gloves boxes using surfactants in CO2 supercritical fluid are given.<br />
<strong>Final</strong>ly, the major challenges to develop more secure processes and to reach a better decontamination efficiency are given.<br />
5) DECOMMISSIONING OF THE A-1 NPP HEAVY WATER EVAPORATOR FACILITY (wP-59225)<br />
Jan Medved, VUJE Inc.; Ladislav Vargovcik, ZTS VVU Kosice a.s. (Slovakia)<br />
The paper deals with experience and techniques in the application of remotely controlled robotic devices for the dismantling<br />
of the A-1 NPP technological equipment during undergoing decommissioning process of the A-1 NPP, which is characterized by<br />
high level of radioactivity and contamination. For liquidation of the heavy water evaporator has been applied a mobile robotic system<br />
MT 80, which had been developed, designed and constructed as a general-purpose decommissioning equipment. The heavy<br />
water evaporator as a part of the NPP heavy water system is located inside the main production unit building in Room No. 220<br />
where the inner surface contamination is from 101 Bq/cm2 to the level of 103 Bq/cm2 , dose rate up to 1.5 mGy/h and the feeding<br />
pipeline contained LRAW with high tritium content.<br />
The first step was the development of a work procedure with special focus on the elimination of activity and aerosols leaking<br />
into the environment. Special tooling was developed for application with the robot, such as hydraulic shears, circular saw, reciprocating<br />
saw, circular pipe cutter and a system for quick tool-change without direct intervention of the operators. Then, civil engineering<br />
modifications were made to the workplace and new technology was installed, including an efficient exhaust…<br />
6) REMOTE DECOMMISSIONING OF BLIND CELLS - APM 214 FACILITY CEA MARCOULE (w/oP-59206)<br />
Olivier Calixte, ONET Technologies - ONECTRA (France)<br />
The APM 214 facility (Marcoule Pilot Workshop) owns blind cells which were used to realize some chemical process operations.<br />
These ones are at their end of life and D&D operations are planned.<br />
Due to the high level of radiations these operations must be partially realized with remote machines. The CEA has entrusted<br />
ONECTRA, a subsidiary of ONET TECHNOLOGIES to define the best way to dismantle these blind cells by remote operations.<br />
The first step started with an inventory of main physical characteristics, constraints, nature of remote operations to do and possible<br />
tools.<br />
7) TRANSPORT OF NUCLEAR WASTE FLOWS - A MODELING AND SIMULATION APPROACH (wP-59136)<br />
Jonathan Adams, Michael Fairweather, James Young, Simon Biggs, Jun Yao, University of Leeds, Leeds (UK)<br />
The task of implementing safer and more efficient processing and transport techniques in the handling of nuclear wastes made<br />
up of liquid-solid mixtures provides a challenging and interesting area of research. The radioactive nature of nuclear waste means<br />
that it is difficult to perform experimental studies of its transport. In contrast, the use of modelling and simulation techniques can<br />
help to elucidate the physics that underpin such flows and provide valuable insights into common problems associated with them,<br />
as well as assisting in the focussing of any experimental studies. With nuclear waste in the form of solid-liquid sludges it is important<br />
to understand the nature of the flow, with particular interest in the settling characteristics of the particulate waste material.<br />
Knowledge of the propensity of pipe flows to form solid beds is important in avoiding unwanted blockages in pipelines and pumping<br />
systems. In cases where the formation of a solid bed is unavoidable, it is similarly important to know how the modified crosssectional<br />
area of the pipe, due to the presence of a bed, will affect particle behaviour through the creation of secondary flows. A<br />
greater understanding of particle deposition in pipes of circular cross-section is also of significant and…<br />
8) FUEL RACKS DISMANTLING WORKSHOP AT CENTRACO FACILITY (wP-59365)<br />
Jean-François Rives, Christophe Maufrais, SOCODEI (France)<br />
Initial context: EDF aims to replace all the ancient storage racks to gain place in the fuel ponds. This project represents about<br />
450 units up to 4m x 4,4m x 2,9m, weight 6,4te to dismantle, during 5 years The average density of the racks is very low (approx<br />
~ 0.15). Due to this low density, final repository route is not adapted. By its knowledge and capabilities, CENTRACO route was<br />
chosen to reduce volume, restore density, decontaminate & secure the elimination of the racks. With those data, CENTRACO has<br />
defined the ATG workshop to dismantle racks but also wide components as steam generators. It was designed with as much automated<br />
devices and skills as possible, in order to avoid dose rate and contamination and to save time. It is currently under construction<br />
and will be put in operation in the early 2012.<br />
87
Session 27 Abstracts<br />
SESSION 27 — ER SITE CHARACTERIZATION AND MONITORING - PART 1 OF 2 (4.5)<br />
1) SOILS RADIOLOGICAL CHARACTERIZATION UNDER A NUCLEAR FACILITY (wP-59046)<br />
Emilie Aubonnet, Geovariances / CEA FAR, Fontenay aux Roses, France,<br />
Didier Dubot, CEA/FAR/USLT/SPRE/SAS, Fontenay aux Roses (France)<br />
Nowadays, nuclear industry is facing a crucial need in establishing radiological characterization for the appraisal and the monitoring<br />
of any remediation work. Regarding its experience in this domain, the French Atomic Energy Commission (CEA) of Fontenay-aux-Roses,<br />
established an important feedback and developed a sound methodology for radiological characterization.<br />
This approach is based on several steps: • historical investigations • assumption and confirmation of the contamination • surface<br />
characterization • in depth characterization • rehabilitation objectives • remediation process<br />
In this methodology the amount of measures, samples and analysis is optimized for data treatment by geostatistics. This innovative<br />
approach is now used to characterize soils under facilities. In Fontenay-aux-Roses CEA Centre, there is an action plan aiming<br />
to assess the activity level under accessible facilities. The paper presents the radiological characterization of soils under RM1<br />
basement. This facility has been built after the first generation of nuclear facilities in place of a plutonium facility which has been<br />
dismantled in 1960. The presentation details the different steps of radiological characterization from historical investigations to<br />
optimization of excavation depths, impact studies and contaminated volumes.<br />
2) RADIOLOGICAL EVALUATION OF CONTAMINATED SITES AND SOILS VEGAS:<br />
AN EXPERTISE AND INVESTIGATING VEHICLE (wP-59057)<br />
Julien Attiogbe, GEOVARIANCES; Marie Lavielle, Patrick De Moura, CEA (France)<br />
The "Commissariat à l’Energie Atomique" (CEA, French Atomic Energy Commission) has set up over the last 10 years<br />
an innovative methodology aiming at characterizing radiological contaminations. The application of the latter relies on various tools<br />
such as recently developed software platform called Kartotrak which is used in the expertise vehicles with impressive detection performances<br />
(VEgAS). A Geographic Information System tailored to radiological needs constitutes the heart of the platform; it is surrounded<br />
by several modules dedicated to sampling optimization, data analysis and geostatistical modeling, real-time monitoring<br />
(Kartotrak-RT) and validation of proper clean-up operations. This paper presents the purpose and the performances of the VEgAS<br />
which provides exhaustive instruments for the radiological surface characterization of sites.<br />
3) DETERMINATION OF THE RADIONUCLIDE CONTAMINATION<br />
ON THE ABSHERON PENINSULA IN AZERBAIJAN (wP-59177)<br />
Tjalle Vandergraaf, Providence University College; Gudrat G Mamedov, Mahammadali A. Ramazanov,<br />
Baku State University; Jalal A. Naghiyev, Institute of Radiation Problems; Afat A. Mehdiyeva, National Aerospace<br />
Agency of Azerbaijan; Nazim A. Huseynov, Institute of Radiation Problems (Canada/Azerbaijan)<br />
Much of Azerbaijans Absheron Peninsula is contaminated by natural U-series and Th-series radionuclides, released in the production<br />
of oil and gas and, to a lesser extent, by anthropogenic radionuclides, including Sr-90 and Cs-137, from local industrial<br />
activities and trans-border transport. The region contains a large number of pipelines and artificial lagoons that have been used to<br />
retain excess groundwater and oil residues. In spite of the long history of the oil and gas industry, radioecological investigations<br />
have not been carried out until recently.<br />
The purpose of the current project is to determine the extent of radionuclide contamination in the Absheron Peninsula using a<br />
combination of radiation field measurements and laboratory analysis of selected samples, focusing on ten routes in the vicinity of<br />
Baku. The routes were selected as most likely to have become contaminated over time. Soil samples, taken from surface and to a<br />
depth of 1 m, aqueous samples from surface waters and marshes, and aqueous and sediment lagoons that showed elevated dosimetry<br />
readings, were analyzed by gamma spectrometry. Control samples were taken form non-contaminated areas. Samples of air and<br />
surface waters were analyzed for Rn-220 and Rn-222. The data will then be used to assess the potential impact<br />
4) HIGH-DENSITY GAMMA RADIATION SPECTROMETRY SURVEYS OF CONTAMINATED LAND (wP-59076)<br />
Mike Davies, Robert Clark, Ian Adsley, Nuvia Limited (UK)<br />
The design of gamma radiation surveys of contaminated land has always had to compromise between the density of sampling<br />
and the accuracy of measurement. Large-area contamination is readily detected by a variety of measurement techniques, while the<br />
detection of small areas or particles requires a high density of measurement, generally one measurement per square metre.<br />
High Resolution Gamma-radiation Spectrometry (HRGS) can provide accurate qualitative (radionuclide identification) and<br />
quantitative (Bq.g-1 of the radionuclide for a stated scenario) assessment of the state of the land, but are not cost effective at high<br />
density. In contrast, simple walk-over or scan surveys using standard Health Physics instruments can provide a high density of<br />
measurement, but cannot provide the qualitative and quantitative accuracy of HRGS. In 1996, Nuvia Limited adopted methods to<br />
address some of these issues, by allowing scan surveys to include a degree of qualitative analysis of the gamma radiation detected<br />
using Low Resolution Gamma-radiation Spectrometry systems with Sodium Iodide detectors, while maintaining a high density of<br />
measurement.<br />
While low-resolution systems (including medium-resolution Lanthanum Bromide) have become the de-facto standard for large<br />
area land surveys, the use of the technology has changed little. High density scan surveys can be conducted using, for example,…<br />
88
Abstracts Session 27<br />
5) REMEDIATION AND ASSESSMENT OF THE NATIONAL RADIOACTIVE WASTE<br />
STORAGE AND DISPOSAL SITE IN TAJIKISTAN (wP-59110)<br />
Nazirzhon Buriev, Dzhamshed Abdushukurov, Physical-Technical Institute of the Academy of Sciences<br />
of the Republic of Tajikistan; Tjalle Vandergraaf, Providence University College (Tajikistan/Canada)<br />
The National Radioactive Waste Storage and Disposal Site was established in 1959 in the Faizabad region approximately 50<br />
km east of the capital, Dushanbe. The site is located on the southern flank of the Fan Mountains facing the Gissar Valley in a sparsely<br />
populated agricultural area, with the nearest villages located a few km from the site. The site was initially designed to accept a<br />
wide range of contaminated materials, including obsolete smoke detectors, sealed radioactive sources, waste from medical institutions,<br />
and radioactive liquids.<br />
6) INTEGRATING HISTORY AND MEASUREMENT INTO A CASE FOR SITE RELEASE (wP-59131)<br />
Angela Bartlett, Research Sites Restoration Limited; Mike Davies, Pete Burgess, Nuvia Ltd;<br />
Gavin Coppins, Babcock International Group (UK)<br />
The United Kingdom nuclear research programme started in the 1940s. Research Sites Restoration Limited (RSRL) is responsible<br />
for two sites which were at the forefront of this research. These are the 100 hectare Harwell site in Oxfordshire and the 84<br />
hectare Winfrith site on the south coast of England. The work performed on these sites covered a huge range of nuclides, combinations<br />
of nuclides, chemical and physical processes, far more complicated than a power station, for example. The sites have a complex<br />
history with records of hundreds of buildings, many kilometres of drainage systems, groundwater contamination issues and<br />
land areas which require remediation. Formal work towards site release began in the 1990s, but demolition and clearance for reuse<br />
started many years earlier.<br />
An efficient restoration programme requires appropriate quality data. It is vital to decide what you need to know and how well<br />
you need to know it. As part of this, a challenging number of factors need to be considered in its design.<br />
This paper discusses these factors using the examples of the approach used at the Harwell and Winfrith sites including:<br />
• historical knowledge and associated uncertainties<br />
• relevant clearance criteria<br />
• availability and limitations of surveying equipment...<br />
7) CHARACTERIZATION OF A DEEP RADIOLOGICAL CONTAMINATION:<br />
INTEGRATION OF GEOSTATISTICAL PROCESSING AND HISTORICAL DATA (wP-59062)<br />
Yvon Desnoyers, GEOVARIANCES; Patrick De Moura, CEA (France)<br />
Emerging in the early 80s, decommissioning is more than ever a major issue since hundreds of sites and facilities worldwide<br />
will end their operations over the next decades. Decontamination and remediation projects are all the more sensitive since they<br />
could last several years and turn out to be highly costly if not well-prepared. The key lies in an adequate contamination knowledge<br />
which helps to manage the remediation works and optimize the radiological waste production.<br />
The methodologies commonly applied base their recommended decision-process on more or less complex statistical analyses<br />
to validate the remediation target after the waste removal work (guidance for demonstrating compliance with a dose- or risk-based<br />
regulation). These techniques ignore the spatial behavior of the contamination and the importance of sample localization upstream.<br />
The lack of representation and data processing tools leads to inefficient radiological characterizations, which always maximize the<br />
amount of contaminated soils or concrete volumes.<br />
To solve these issues, the French Atomic Energy Authority (CEA) has developed a methodology over the last 10 years with<br />
Geovariances partnership to fulfill the radwaste categorization. This methodology consists of an ordered sequence of evaluation<br />
actions starting with historical and functional analyses, in-situ characterization if relevant using non-intrusive measurement techniques,<br />
...<br />
8) INDUSTRIAL EXPERIENCE FEEDBACK OF A GEOSTATISTICAL ESTIMATION<br />
OF CONTAMINATED SOIL VOLUMES (wP-59181)<br />
Claire Faucheux, Nicolas Jeannée, GEOVARIANCES(France)<br />
Data collected during the sampling of polluted sites are mainly used to characterize the concentration level and, through an<br />
exploratory and variographic analysis, to characterize the spatial variability; at fixed support, to estimate the concentrations in order<br />
to trace pollution map. In the case of kriging, this map is completed by the map of the standard deviation of the estimation error,<br />
making it possible to delimit the zones in which the estimation is considered to lack in precision. If a proportional effect is present<br />
(the local spatial variability depends on the local concentrations mean), the map of error standard deviation has to be corrected to<br />
take into account the increase of spatial variability with the local concentration mean.<br />
A confidence interval can be derived conventionaly from the kriging estimation and the associated error standard deviation.<br />
For a fixed limit threshold, the polluted site can then be divided in three areas:<br />
• the polluted zone, at a fixed statistical risk;<br />
• the not polluted zone, at a fixed statistical risk;<br />
• the zone of uncertainty , in which the estimated concentrations are close to the threshold. Because of the estimation error,<br />
it is not possible to specify if the exact concentrations exceed or not the threshold.<br />
In the case of a soil pollution by hydrocarbons, usual and geostatistical forecasts are compared. The effective consequences of<br />
these various forecasts on the quality of the site remediation are quantified and discussed.<br />
89
Session 28 Abstracts<br />
SESSION 28 — PUBLIC PERCEPTION ISSUES AND STAKEHOLDER ENGAGEMENT STRATEGIES<br />
IN RADIOACTIVE ENVIRONMENTAL MANAGEMENT (5.5)<br />
1) PERSPECTIVES ON REVERSIBILITY AND RETRIEVABILITY OF A<br />
GEOLOGICAL REPOSITORY IN FRANCE (wP - 59263)<br />
Jean-Noel Dumont, Jean-Michel Hoorelbeke, Andra (France)<br />
In France it is required by law that the future geological repository for HLW and ILLW be reversible. Reversibility reflects<br />
social and political demand. The law, however, does not provide conditions for implementing reversibility. Instead, it calls upon<br />
scientists to issue specific proposals before a new law is promulgated as a preliminary to obtaining authorization to build a waste<br />
repository. A dialogue between various players, scientists and stakeholders is required to prepare these proposals. It gives designers<br />
of the repository the opportunity to assess social expectations and integrate them. It is also an opportunity to examine together<br />
possible technologies, as well as scientific and technical limits. Andra is involved in various forms of dialogue with social players.<br />
Several expectations related to reversibility have been detected by Andra through this dialogue. Reversibility means in particular<br />
retrievability of waste package(s) once disposed, which could be envisaged if future technical progress makes it re-useable, to<br />
switch to another mode of waste management, or if the repository does not evolve as planned. More generally, the demand for<br />
reversibility reflects the desire to control evolution of the process and make sure that the repository will not be abandoned after closure.<br />
These expectations call for answers…<br />
2) A DIALOGUE-CENTRIC APPROACH TO ENVIRONMENTAL REMEDIATION DECISION-MAKING (wP -59115)<br />
Laurel Boucher, The Laurel Co.; James Clark, CRX Group, Inc. (USA)<br />
This paper outlines a multi-step approach to streamline and enhance the decision-making process that guides environmental<br />
remediation. The inability of the responsible party and the various stakeholders to reach agreement on the remediation plan can<br />
delay the remediation, result in financial penalties, and lead to the development of an adversarial stance that inhibits the ability of<br />
the parties to work together in a creative and constructive manner. The approach presented by the authors is designed to expand<br />
dialogue in a way that moves it beyond technical or fiscal matters by addressing what the authors describe as the hidden barriers<br />
to productive dialogue. These hidden barriers include: self-interests, the perception as to how people are being treated, a lack of<br />
clarity or poor management of responsibilities and accountabilities, unclear or convoluted communication protocols, and an underlying<br />
tone of conflict and cynicism. A key element of the multi-step approach outlined in this paper is the process of uncovering<br />
these hidden barriers and addressing them in a way that turns discourse into collaboration.<br />
The paper describes a model the authors have used to streamline and enhance the process of creating sustainable agreements<br />
both for the U.S. Department of Energys Office of Environmental Management…<br />
3) OUTREACH AND EDUCATION - ENSURING A CLEAN ENERGY FUTURE FOR ALL (wP - 59339)<br />
Susan Hess, Areva Inc USA)<br />
As the nuclear industry continues to grow throughout the world, we find that support from government officials, local business<br />
leaders and the general public is becoming more and more important.<br />
In order to help raise awareness and inform these various publics, AREVA expanded upon a best practice from its worldwide<br />
operations and recently established a Community Advisory Council in the United States. The member organizations represent a<br />
variety of grassroots and minority organizations from across the United States and are active in various ways in local, state and federal<br />
arenas.<br />
4) CHALLENGE IN THE PUBLIC ACCEPTANCE AND COOPERATION IN THE VERGE OF<br />
BUILDING THE FIRST NUCLEAR POWER PLANT IN INDONESIA (wP - 59119)<br />
Putero Susetyo Hario, Santosa Haryono Budi, Gadjah Mada University (Indonesia)<br />
Indonesia plans to build the first nuclear power plant (NPP) to solve the country’s energy problems. One of the challenges that<br />
must be handled before establishing the first NPP is the presence of anti-nuclear groups that have successfully made the government<br />
postpone its plan several times since the first nuclear research reactor was established in Bandung (1972). The basis for the<br />
groups’ dissent is the presence, and handling of radioactive waste. Further, the general public perception – even among educated<br />
Indonesians – is that Indonesia’s experts lack knowledge about nuclear technology, even though nuclear technology has been studied<br />
in Indonesia since 1954.<br />
So, the problem is one of disseminating information about nuclear technology. To address this challenge, the National Atomic<br />
Energy Board (BATAN) of Indonesia has to redesign its public outreach strategy by collaborating with the educational institutions<br />
and communications organizations. Gadjah Mada University is the only university in Indonesia offering a nuclear-engineering curriculum.<br />
Therefore, a teaming arrangement with this institution seems appropriate to help improve the public’s general knowledge<br />
about nuclear technology. There are several strategies that could be designed within the frame work of collaboration. The first strategy<br />
is to introduce nuclear technology into Indonesia’s elementary and secondary schools. These youngsters are still in their formative<br />
years and are absorbing science and technology with great attention.<br />
5) ANDRA LONG TERM MEMORY PROJECT (wP - 59277)<br />
Patrick Charton, Fabrice Boissier, Guillaume Martin, Andra (France)<br />
Long term memory of repositories is required by safety, reversibility and social expectations. Thus Andra has implemented<br />
since 2010 a long-term memory project to reinforce and diversify its current arrangements in this field, as well as to explore opportunities<br />
to extend memory keeping over thousands years.<br />
90
Abstracts Session 29<br />
The project includes opportunity studies of dedicated facilities. The écothèque and géothèque projects contribute to memory<br />
respectively through environmental and geological samples preservation. The options of creating (i) an archive centre for Andras<br />
interim and permanent archives, (ii) an artist center to study the contribution of arts to memory preservation, (iii) a museum of<br />
radioactive waste disposal history and technology (radium industry..., sea disposal&, current solutions...) are considered.<br />
Other studies provided by the project examine our heritage. This includes the continuity of languages and symbolic systems,<br />
the continuity of writing and engraving methods, the archaeology of landscapes (memory of the earths evolution, multi-century<br />
memory of industrial and agricultural landscapes&), the archaeology practices (how might a future archaeologist be interested in<br />
our current activity?), the preservation of historical sites and industrial memory, the continuity of institutional organizations, the<br />
memory and history of science evolution as well as broad history.<br />
Significant studies address social issues, such...<br />
6) ENGAGING LOCAL STAKEHOLDERS ON TECHNICAL ISSUES:<br />
TEST CASE AT THE LA HAGUE REPROCESSING PLANT (wP - 59211)<br />
Ludivine Gilli, Institut de radioprotection et de sûreténucléaire (IRSN) (France)<br />
As the French public expert in the nuclear field, the Institute for Nuclear Safety and Radioprotection (IRSN) has for several<br />
years advocated the need to engage citizens on technical issues pertaining to radioactive waste management. This belief in the usefulness<br />
of citizens involvement to enhance nuclear safety has led IRSN to initiate numerous pilot actions in cooperation with local<br />
actors.<br />
In 2009-2010, IRSN tackled a new pilot action regarding the decommissioning of the HAO (High Activity Oxide) workshop,<br />
located on Arevas fuel reprocessing plant site, in La Hague, North-western France. The purpose of that action was to experiment<br />
ways for IRSN and local actors to engage in technical discussions with a concrete objective in mind: contributing to enable the local<br />
stakeholders to take a stand on the operators decommissioning application.<br />
A pilot action was useful here, because the challenges are many when it comes to engaging with citizens on technical matters.<br />
First, there is a significant knowledge and cultural gap between most local stakeholders and the nuclear professionals, which<br />
prevents the formers to get a grip on technical issues. Hence, both parts must make an effort to understand and be understood. The<br />
local actors must moreover build a technical capacity...<br />
7) CREATING AND MANAGING RADIOACTIVE WASTE DISPOSAL FACILITIES<br />
WITH THE INVOLVEMENT OF THE LOCAL POPULATIONS (w/oP - 59286)<br />
Sébastien Farin, Andra (France)<br />
Andra is responsible for proposing and implementing industrial management solutions for all French radioactive waste. Andra<br />
is in particular in charge of operating the two repositories in the Aube region, monitoring the Manche repository one of the world’s<br />
first surface repositories and creating disposal facilities for waste currently without an operational disposal solution.<br />
Andra’s communication approach.<br />
Andra’s communication role is stipulated by law and is an integral part of its activities, in the same way as research, industry<br />
or risk management. Andra’s aim is to make the subject of radioactive waste management one that is of nationwide interest comprehensible<br />
to the largest possible number, so that each citizen and stakeholder can, in full possession of the facts, make his or her<br />
own opinion and finally reach an informed decision.<br />
Andra’s communication policy is based on four main levers:<br />
• Information, through a full range of tools (websites, publications, periodicals) adapted to the level of expertise and understanding<br />
of its various target audiences;<br />
• Explanation, by means of opportunities throughout the year for those interested in the subject (site visits, fairs, meetings<br />
with schools, travelling exhibitions, etc.);<br />
• Local integration, through regular relations with local players and ...<br />
SESSION 29 — PANEL: INTERNATIONAL COOPERATION:<br />
NEA ROAD MAP, HOW TO INCREASE SYNERGY (3.12)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 30 — SITING, DESIGN, CONSTRUCTION, AND OPERATION<br />
OF L/ILW DISPOSAL FACILITIES - PART 1 OF 2 (1.12)<br />
1) AN INNOVATIVE DESIGN FOR LOW AND INTERMEDIATE RADWASTE NEAR<br />
SURFACE REPOSITORY IN LITHUANIA (w/oP-59382)<br />
Boniface Jean-Michel, AREVA TA (France)<br />
In 2009, in response to an open tender, funded by the European Bank for Reconstruction and Development, a consortium comprising<br />
Lithuanian and French partners led by Areva was selected by Ignalina nuclear power plant (INPP) to design a dedicated<br />
100.000 m3 LILW-SL Near Surface Repository (NSR) planned to be constructed nearby the power plant.<br />
After preliminary siting studies, the site of Stabatiske was selected by the Lithuanian government in 2007. Following this decision,<br />
the projects technical and commercial requirements for the NSR design was prepared by experts from INPP with the support<br />
of the Lithuanian radwaste management agency (RATA).<br />
This NSR is to be developed and engineered for the disposal of INPP radwaste produced by its operation, and arising from its<br />
dismantling. The result of the project is to develop, following IAEA guidelines, an innovative multi-barrier repository design which<br />
is engineered for the Stabatiske site, with the presence of groundwater, for the sites characteristics, comprising clay layers, moraine<br />
deposits and aquifers, and for the volume and type of radwaste, the disposal containers and the engineered barriers. This design is<br />
on schedule for completion in 2013, and will provide the basis for the construction of the repository, the first facilities of…<br />
91
Session 30 Abstracts<br />
2) PRODUCT QUALITY CONTROL OF RADIOACTIVE WASTE WITH A SPECIAL REGARD<br />
TO FEDERAL STATES COLLECTING FACILITIES (w/oP-59176)<br />
Markus Havertz, Research Centre Jülich GmbH (Germany)<br />
The KONRAD repository for low- and intermediate level radioactive waste is the first disposal facility approved by the Atomic<br />
Energy Act in Germany.<br />
For final disposal the radioactive waste products or waste packages have to meet the acceptance criteria of the final repository<br />
KONRAD.<br />
On behalf of the Federal Office for Radiation Protection the quality control group (PKS) at Research Centre Jülich accomplishes<br />
the product quality control of non-heat producing waste, which mainly arises from generation of electricity by nuclear power<br />
plants, research and development activities, medicine and industry, as well as decommissioning and dismantling of nuclear facilities.<br />
The product quality controlling process includes varies steps, inter alia checks of product quality control plans to be appropriate<br />
for the conditioning purposes, on site inspections to control the quality of the waste form, checks of waste package inventory<br />
declarations and accompanying waste package documentations with regard to the KONRAD specifications.<br />
According to the Atomic Energy Act the German Federal States have to establish State Collecting Facilities (FSCS) for the<br />
interim storage of the radioactive waste originating in their territories. The FSCFs deal in general with low active wastes arising in<br />
nuclear medicine and at smaller research facilities (universities, industrial and health…<br />
3) CENTRE DE LA MANCHE: A DISPOSAL FACILITY IN INSTITUTIONAL CONTROL (wP-59236)<br />
Michel Dutzer, Jean Pierre Vervialle, Alain André, Albert Marchiol, Andra (France)<br />
Centre de la Manche disposal facility is the first French surface disposal facility dedicated to low and intermediate level short<br />
lived radioactive waste. It started up in 1969. After a continuous improvement, in the design of disposal vaults, in operational<br />
modes, in the whole process of waste management, in the safety approach, the last packages were received in 1994. 527,000 m3 of<br />
waste packages have been disposed during the 25 years of operation. The facility was licensed for the institutional control period<br />
in 2003.<br />
The disposal vaults are covered with a multilayer capping system that includes a bituminous membrane to provide protection<br />
against rainwater infiltration. Water that might infiltrate through the membrane is collected by the bottom slab of the vaults to a<br />
pipe network implemented in an underground gallery. Measurements show an overall infiltration rate of about 2.7 l/m2 /year that<br />
complies with the objective of Andra of a few liters per square meter and per year.<br />
Investigations are performed in order to assess the behavior of the membrane in the long term. For this purpose periodically<br />
samples of the bituminous membrane are taken and measurements are performed.<br />
As at the beginning of the operational period waste packages were not…<br />
4) RADIOLOGICAL IMPACT OF CO-LOCATION OF THE VLLW AND<br />
LILW REPOSITORY AT MOCHOVCE SITE (wP-59152)<br />
Václav Hanusík, Zdena Kusovská, Jozef Morávek, VUJE, Inc.;<br />
J. Balaz, O. Chren, Nuclear and Decommissioning Company plc. (Slovakia)<br />
JAVYS, the Nuclear Decommissioning Company owner and operator of National Radioactive Waste Repository (NRR) at<br />
Mochovce, is planning the enlargement of the existing NRR. The enlargement consists of the construction of new structures (double<br />
rows) like the ones existing for LILW and of the new facility for the disposal of Very Low Level Waste (VLLW). A VLLW disposal<br />
site is being planned in Mochovce where a LILW disposal site is already located. As a part of ongoing licensing process for<br />
this change in utilization of the NRR we have updated the already existing assessment of potential radiological impact to members<br />
of the public after closure of the site, both from the migration of leachate in groundwater from the site and from possible inadvertent<br />
intrusion into the site, including future residence on the material excavated for the construction of the road. The radionuclides<br />
from the ground water reach the biosphere through a spring flowing into the lake. It is conservatively assumed that individual in<br />
the critical group uses biosphere of the lake (for irrigations, fishing and recreation). In the case of unintentional intrusion into the<br />
repository, the exposed group consists of a small number of workers who excavate or examine repository<br />
5) DEVELOPMENT OF AN ENGINEERING DESIGN PROCESS AND ASSOCIATED SYSTEMS<br />
AND PROCEDURES FOR A UK GEOLOGICAL DISPOSAL FACILITY (wP-59160)<br />
Philip Rendell, NDA; Henry O’Grady, Parsons Brinckerhoff: Brendan Breen, Alastair Clark, Steve Reece, NDA (UK)<br />
In the United Kingdom the Nuclear Decommissioning Authority (NDA) has been charged with implementing Government policy<br />
for the long-term management of higher activity radioactive waste. The UK Government is leading a site selection process<br />
based on voluntarism and partnership with local communities interested in hosting such a facility and as set out in the Managing<br />
Radioactive Waste Safely White Paper (2008).<br />
The NDA has set up the Radioactive Waste Management Directorate (RWMD) as the body responsible for planning, building<br />
and operating a geological disposal facility (GDF). RWMD will develop into a separately regulated Site Licence Company (SLC)<br />
responsible for the construction, operation and closure of the facility. RWMD will be the Design Authority for the GDF; requiring<br />
a formal process to ensure that the knowledge and integrity of the design is maintained.<br />
In 2010 RWMD published Geological Disposal - Steps towards implementation which described the preparatory work that it<br />
is undertaking in planning the future work programme, and the phases of work needed to deliver the programme. RWMD has now<br />
developed a process for the design of the GDF to support this work. The engineering design process follows a staged approach,<br />
encompassing options development, requirements definition, and conceptual and detailed…<br />
92
Abstracts Session 31<br />
6) STATE OF THE ART FOR FABRICATING AND EMPLACING CONCRETE CONTAINERS INTO LARGE<br />
HORIZONTAL DISPOSAL CAVERNS IN THE FRENCH GEOLOGICAL REPOSITORY (wP-59267)<br />
Jean-Michel Bosgiraud, Maurice Guariso, François Pineau, Andra (France)<br />
The research and development work presented in this paper was initialized by Andra in 2007. The work necessary for manufacturing<br />
and testing a full scale demonstrator is presently implemented. The case story is twofold.<br />
The first part is related to the initial development of a high performance concrete formulation used for fabricating concrete storage<br />
containers (containing Medium Level and Long Lived Waste<br />
primary canisters) to be stacked and emplaced into 400-m long concrete lined horizontal disposal vaults (also called caverns,<br />
excavated in the Callovo-Oxfordian clay host formation at a 550 to 600-m depth) with an inside diameter of approximately 8-m.<br />
The concrete formulation qualification process is described and the design and fabrication case story of the concrete boxes is<br />
detailed. The rationale of the concept, the basics of its formulation and the technical achievements and performances obtained at<br />
the end of the fabrication phase are described.<br />
The second part presents the outcome at the end of the detailed design phase, for a system which is now being manufactured<br />
(for further test and assembly) for the emplacement of the concrete containers inside the vault. The application was engineered for<br />
remote emplacing a pile of 2 concrete containers (the containers are preliminarily…<br />
7) ON-SITE, NEAR SURFACE DISPOSAL OF GRAPHITE WASTES IN THE UK (wP-59078)<br />
Adam Meehan, Peter Sibley, EnergySolutions; Jeremy Lightfoot, Golder Associates (UK) Ltd.;<br />
Duncan Jackson, Eden Nuclear & Environment Ltd., (UK)<br />
Reactor graphite makes up about 30% by volume of the UKs inventory of intermediate level waste (ILW). There is estimated<br />
to be about 15,000m3 of graphite arisings prior to 2040, mainly comprising operational waste streams (Magnox and AGR fuel<br />
sleeves), along with core graphite from the decommissioning of experimental and prototype reactors. A further 65,000m3 of<br />
graphite is forecast to arise after 2040, comprising core graphite from the final decommissioning of the Magnox and AGR reactors.<br />
Consequently, the management and disposal of graphite wastes is of key strategic importance in the UK.<br />
The current baseline strategy for reactor graphite wastes in the UK is to encapsulate them upon retrieval using a cementitious<br />
grout in stainless steel Nirex containers in accordance with NDA Radioactive Waste Management Directorate (RWMD) Letter of<br />
Compliance (LoC) specifications, and to dispose of them following a period of interim storage to the UKs planned geological disposal<br />
facility (GDF), when this becomes available, currently planned for around 2040.<br />
Using Magnoxs Hunterston A site as a Pathfinder, EnergySolutions and its partner organisations have been engaged with the<br />
feasibility assessment, options assessment, engineering concept design and environmental safety case development for a proposed<br />
on-site, near surface disposal facility for operational…<br />
SESSION 31 — L/ILW WASTE CHARACTERIZATION, ASSAY, AND TRACKING SYSTEMS - PART 2 OF 2 (1.18)<br />
1) NON-DESTRUCTIVE EXAMINATION OF TRU WASTE IN LOW AND HIGH DENSITY<br />
BOXES AND DRUMS, USING HIGH ENERGY REAL TIME RADIOSCOPY (HE-RTR)<br />
AND WIDE DYNAMIC RANGE IMAGING (wP-59302)<br />
Stephen Halliwell, VJ Technologies Inc. (USA)<br />
The Waste Isolation Pilot Plant (WIPP), the cornerstone of the Department of Energys nuclear waste cleanup effort, is designed<br />
to permanently dispose of transuranic (TRU) radioactive waste. Real time radioscopy (RTR) using x-ray energies of up to 450keV,<br />
has been used extensively for the non-destructive examination (NDE) part of the characterization and certification of waste drums<br />
and low density waste boxes, prior to shipment to WIPP. However, to characterize drums and boxes containing a mixture of both<br />
low and high density waste, x-ray energies of up to 6MeV, together with an x-ray imaging system having a wide dynamic range,<br />
are required. The system, including the high energy vault, is required to be stand-alone, weatherproof and re-locatable, and must<br />
be fully compliant with ANSI.N43.3, classified as an exempt shielded facility for x-ray energies up to 6MeV.<br />
This paper describes the design, build and operation of the new generation of high energy RTR systems now being used in the<br />
characterization of waste destined for disposal at WIPP.<br />
Importance of this work. Characterization of TRU waste in boxes and drums by non-destructive examination reduces the need<br />
to open the containment and to visually examine the waste. The immediate benefits are a reduction in risk of operator dose uptake,<br />
a reduction in the generation of additional waste, and the saving of time and cost within the process.<br />
2) MEASUREMENT METHODOLOGY FOR FULFILLING OF WASTE ACCEPTANCE CRITERIA<br />
FOR LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTE IN STORAGES (wP-59016)<br />
Marina Sokcic-Kostic, Felix Langer, Roland Schultheis, NUKEM Technologies GmbH (Germany)<br />
Low level and intermediate level radioactive waste must be sorted and treated before it can be sent to radioactive waste storage.<br />
A variety of parameters must be considered to fulfil the acceptance criteria for these storages. NUKEM Technologies has a<br />
long time experience with the erection and management of radioactive waste treatment facilities and has developed methods and<br />
equipment to produce the waste packages where all the required information are compiled.<br />
The preferred methods are the non-destructive methods, which allow high throughput and give detailed information.<br />
The required waste acceptance information is divided into physical, chemical and radiological aspects. Experience has shown<br />
that different strategies have to be applied for their acquisition: the radiological information is acquired by measurements, whereas<br />
the physical and chemical information is gathered from origin of waste, sorting and treatment procedures. In rare cases direct<br />
measurements are applied in addition: the example for this is the grouting process.<br />
The tracking data base system developed by NUKEM Technologies tracks the waste streams through the waste treatment facility<br />
and combines the gathered information from the delivered waste to generate sophisticated waste declarations for further storage.<br />
Physical and chemical parameters are managed via the tracking methodology, which has proven<br />
93
Session 31 Abstracts<br />
3) DISPOSITION OF TRANSURANIC RESIDUES FROM PLUTONIUM ISENTROPIC COMPRESSION<br />
EXPERIMENT (PU-ICE) CONDUCTED AT Z MACHINE (LA-UR-10-05649) (wP-59186)<br />
Kapil K. Goyal, Los Alamos National Laboratory; Betty J. Humphrey, Weston Solutions Inc.; Jeffry Gluth, Ktech<br />
Corporation/Sandia National Laboratory; David M. French, Los Alamos National Laboratory (USA)<br />
In 1992, the U.S. Congress passed legislation to discontinue above- and below-ground testing of nuclear weapons. Because<br />
of this, the U.S. Department of Energy (DOE) must rely on laboratory experiments and computer-based calculations to verify the<br />
reliability of the nuclear stockpile. The Sandia National Laboratories/New Mexico (SNL/NM) Z machine was developed to support<br />
the science-based approach for mimicking nuclear explosions and stockpile stewardship. Plutonium (Pu) isotopes with greater<br />
than ninety-eight percent enrichment were used in the experiments. In May 2006, SNL/NM received authority that the Z Machine<br />
Isentropic Compression Experiments could commence.<br />
Los Alamos National Laboratory (LANL) provided the plutonium targets and loaded the target assemblies provided by<br />
SNL/NM. Three experiments were conducted from May through July 2006. The residues from each experiment, which weighed<br />
up to 913 pounds, were metallic and were packaged into a 55-gallon drum each.<br />
SNL/NM conducts the experiments and provides temporary storage for the drums until shipment to LANL for final waste certification<br />
for disposal at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. This paper presents a comprehensive<br />
approach for documenting generator knowledge for characterization of waste in cooperation with scientists at the two laboratories<br />
and addresses a variety of essential topics.<br />
4) DETECTION OF SHIELDED SEALED RADIOACTIVE SOURCES IN RADIOACTIVE<br />
WASTE BY NON-DESTRUCTIVE ASSAY TECHNIQUES (wP-59252)<br />
Leo P.M. Velzen, Nuclear Research and Consultancy Group;<br />
Steven van der Marck, Nuclear Research Group (Netherlands)<br />
Experiences dealing with the detection of a SRS or its shielding in waste by non-destructive assay (NDA) methods are seldom<br />
reported in literature. Therefore the main objective of this paper is to assist operators of waste storage facilities or others responsible<br />
for the radiological characterisation of waste that they are able to interpret collected radiological data on the possible presence<br />
of a bare SRS or a shielded SRS.<br />
This objective can be reached by simulating the gamma flux that can be measured on the surface of a waste package containing<br />
a bare or shielded SRS. Appropriate simulations and presentations of the results will illustrate the problems that can occur by<br />
radiological data collection and interpretation in reality.<br />
The simulating calculations have been performed with the Monte Carlo Neutron Photon transport code (MCNP) for gamma<br />
photons of 60Co. Obtained results e.g. gamma and total energy flux are presented in iso-plots to help non-specialist operators interpreting<br />
own collected radiological data to recognize a SRS and dense materials in (historic) waste packages.<br />
The MCNP simulated waste packages have been defined to reflect, as close as possible, reality, i.e. the calculated data are disturbed,<br />
as would be the situation in the case of raw…<br />
5) USE OF LANTHANUM BROMIDE DETECTORS TO AUGMENT<br />
SITE SURVEYS FOR DEPLETED URANIUM (w/P-59169)<br />
Charles Waggoner, Mississippi State University; Ronald Unz, Institute for Clean Energy Technology;<br />
Donna Rogers, Mississippi State University; Charles R. Jones,<br />
Jay P. McCown, Institute for Clean Energy Technology/Mississippi State University (USA)<br />
A variety of systems have now been described for use in surveying sites for anthropogenic radiological contamination. Virtually<br />
all of these include use of sodium iodide detectors and register detection data with global positioning satellite data. This paper<br />
demonstrates how lanthanum bromide detectors can be used to augment existing field surveys in a manner to reduce uncertainty in<br />
areas of low count rates and to discriminate between depleted uranium and naturally occurring uranium.<br />
The survey system described is equipped with large (20 x 20 x 100 cm) sodium iodide (Alpha Spectra) and 7.6 x 7.6 cm lanthanum<br />
bromide (Saint Gobain) detectors. Additional radiological detection equipment (DigiBase) was obtained from ORTEC with<br />
survey data collected in the List Mode. Data collected in surveys were then used to generate digital maps using GeoSofts Oasis<br />
Montaj.<br />
Software has been developed to automatically identify areas of increased count rates using user-defined thresholds. This software<br />
can collect the count data for the masked area and generate a composite spectrum that can be compared to a reference spectrum<br />
believed to represent an uncontaminated area. Ratios of counts attributed to protactinium-234m (Pa-234m) are compared to<br />
counts attributed to Bismuth-214 (Bi-214) for both the composite filed survey spectrum…<br />
6) ULTRASONIC TECHNIQUES FOR THE IN SITU CHARACTERISATION<br />
OF ‘LEGACY’ WASTE SLUDGES & DISPERSIONS (wP-59111)<br />
Timothy Hunter, Jeff Peakall, Simon Biggs, Michael Fairweather, James Young, University of Leeds, Leeds (UK)<br />
Research being undertaken at the University of Leeds, as part of the DIAMOND university consortium, is exploring the effectiveness<br />
of various ultrasonic technologies as in situ probes to characterize and monitor nuclear waste slurries, such as the Legacy<br />
Magnesium hydroxide sludges found in Sellafield, U.K. Through use of a commercial Acoustic Backscatter Sensor (ABS) with 1<br />
5 MHz transducers, various properties of free-settling oxide simulant sludges were determined. Work was focused upon characterizing<br />
essentially static sludges (to give prospective use as tools for the wastes in current deposits); although, the sensors also have<br />
potential as dispersion monitors during any future processing and storage of the Legacy wastes, as well as many other storage, clarifier<br />
or thickener systems across a wide range of industrial processing operations.<br />
ABS data of mixed glass powder dispersions was analysed and compared to scattering theory, to understand the correlations<br />
between acoustic attenuation and particulate concentration. The ABS was also calibrated to measure changes in average particulate<br />
concentration within a settling suspension over time, and showed the depth-wise segregation of the dispersion through the settling<br />
column at different particular time intervals. It was found that observed hindered settling also led to an increase in particulate<br />
concentration…<br />
94
Abstracts Session 32<br />
7) FREE-RELEASE AND SORTING MONITORS DEVELOPED FOR NPP A-1<br />
DECOMMISSIONING, SLOVAKIA (wP-59071)<br />
Ondrej Slávik, VUJE; Alojz Slaninka, VUJE, a.s./ Slovak University of Technology in Bratislava;<br />
Martin Liatjak, Kamil Kravárik, VUJE, a.s.; Igor Pély, JAVYS, a.s. (Slovakia)<br />
Bohunice NPP A-1, Slovakia, was a pilot NPP shut down after nuclear accident with loss of fuel integrity in 1977. Presently,<br />
the 2nd stage of decommissioning project implementation is carrying out. Within this stage of decommissioning it is necessary to<br />
decontaminate, monitor and if possible to free release large amounts of contaminated materials. From point of view of the material<br />
volume to be monitored, contaminated soil and concrete debris are the most crucial ones in this stage (thousands of tons). They<br />
were until now temporary stored in underground basins or similar places within the NPP controlled area. Within the mentioned project<br />
a pilot free-release and sorting monitoring post were developed in order to support the extended need to mentioned monitoring<br />
capabilities.<br />
The main goal expecting to the sorting monitor is to reduce the volume of contaminated materials to be monitored for freerelease.<br />
An operative monitor was designed for this purpose that is based on quick and direct in situ measurements of loader spoon<br />
filled with the excavated materials. A pair of NaI(Tl) detectors is used for the measurements. The spoon is fixed on a covered measurement<br />
frame with automatic fixation logic (pair of rails and an inductive sensor on the…<br />
8) DESIGN AND OPERATION OF THE COMBINED TECHNOLOGY AUTOMATED<br />
WASTE CHARACTERISATION SYSTEM (wP- 59308)<br />
John Mason, Marc R Looman, Robert A. Price, A. N. Technology Ltd. (UK)<br />
This paper describes the design and operation of the Combined Technology Automated Waste Characterisation System (CTA-<br />
WCS) at JRC Ispra. The WCS was designed for the measurement of fission products and uranium and plutonium containing waste<br />
arising from nuclear fuel and nuclear materials processing and reactor operations. The WCS covers a range of activity including<br />
Low and Intermediate Level Waste (LLW and ILW). The system is designed to measure the waste in 200 and 400 (440) litre drums<br />
with a maximum drum weight of 1500 kg. Gamma-ray measurements of radio-nuclide content are performed by a gamma ray measurement<br />
station which functions as either a Segmented Gamma Scanner (SGS) or Tomographic Segmented Gamma-ray Scanner<br />
(TSGS). Either of these two techniques may be employed to perform the functions of drum screening, non-destructive examination<br />
(NDE) and, where appropriate, final drum assay. Coupled to the gamma ray station is a surface dose-rate measurement station,<br />
which employs 6-shielded Geiger-Muller detectors. Active and passive neutron measurements are performed by an advanced,<br />
graphite lined Differential Die-away (DDA) system, which comprises the neutron measurement station. The DDA performs conventional<br />
passive neutron totals, coincidence, and multiplicity counting and active DDA total neutron counting. Data analysis is<br />
based on the use…<br />
SESSION 32 — REPOSITORY PROGRAMS: SITE SELECTION & CHARACTERIZATION,<br />
UNDERGROUND RESEARCH LABS, ENGINEERING & GEOLOGICAL BARRIERS - PART 1 OF 2 (2.3)<br />
1) SAFETY ASSESSMENT INPUT TO SITE SELECTION - THE SWEDISH EXAMPLE (wP-59031)<br />
Johan Andersson, JA Streamflow AB (Sweden)<br />
Svensk Kärnbränslehantering AB (SKB) has performed comprehensive investigations of two candidate sites for a final repository<br />
for Swedens spent nuclear fuel; in Forsmark (municipality of Östhammar) and in Laxemar (municipality of Oskarshamn). In<br />
March 2011 SKB decided to submit licence applications according to the Act on Nuclear Activities and the Environmental Code<br />
for a final repository at Forsmark. The license applications include comprehensive documentation to support that a KBS-3 repository<br />
at Forsmark will meet requirements in laws and regulations, including a full evaluation of long term safety. Before selection,<br />
SKB stated that the site that offers the best prospects for achieving long-term safety in practice would be selected. Based on experiences<br />
previous safety assessments, a number of issues related to long-term safety need to be considered in the context of site comparison.<br />
The factors include sensitivity to climate change such as periods of permafrost and glaciations, rock mechanics evolution<br />
including the potential for thermally induced spalling and sensitivity to potential future earthquakes, current and future groundwater<br />
flow, evolution of groundwater composition and proximity to mineral resources. Each of these factors related to long-term safety<br />
for the two candidate sites is assessed in a comparative analysis of site characteristics. The assessment ...<br />
2) TECHNICAL KNOW-HOW OF SELECTION PROCESS FOR THE HORONOBE<br />
UNDERGROUND RESEARCH LABORATORY AREA AND SITE (wP-59088)<br />
Takanori Kunimaru, Ryuji Takeuchi, Tatsuji Matsuzaki, Japan Atomic Energy Agency (Japan)<br />
The Horonobe Underground Research Laboratory (URL) Project is being pursued by the Japan Atomic Energy Agency (JAEA)<br />
to enhance the reliability of relevant disposal technologies through investigations of the deep geological environment within the<br />
host sedimentary formations at Horonobe, northern Hokkaido, Japan. The project consists of two major research areas, Geoscientific<br />
Research and R&D on Geological Disposal, and proceeds in three overlapping phases, Phase I: Surface-based investigation<br />
Phase, Phase II: Construction Phase and Phase III: Operation Phase, over a period of 20 years.<br />
The early Phase I of the Horonobe URL project consisted of selecting a URL area and URL site, which involved establishing<br />
fundamental factors relating to the geological environment and safety, surface-based investigations of the geological environment,<br />
stepwise narrowing down of candidate or target areas (sites) from the whole Horonobe Town area through candidate URL areas<br />
and, finally, to a URL site.<br />
This study will be demonstrated the selection process for the URL area and URL site in sequence. Horonobe URL has been<br />
declared to be constructed within whole Horonobe Town to be selected early in the fiscal year 2002. The Horonobe URL area/site<br />
is required existence of host argillaceous sedimentary formations and saline groundwater. Further fundamental requirements ...<br />
95
Session 32 Abstracts<br />
3) CHARACTERISATION OF BEDROCK HYDROGEOLOGY AT THE OLKILUOTO<br />
SITE USING SURFACE BASED AND UNDERGROUND DATA (w/oP-59095)<br />
Lee Hartley, Dave Swan, Steven Baxter, SERCO (UK)<br />
Posiva Oy is responsible for implementing the programme for geological disposal of spent nuclear fuel in Finland. Olkiluoto<br />
in Eurajoki has been selected as the primary site for the repository, subject to further detailed characterisation which is currently<br />
focused on the construction of an underground rock characterisation and research facility (the ONKALO). An essential part of the<br />
site investigation programme is analysis of groundwater flow and solute transport to depth by means of numerical flow modelling<br />
as part of the 2011 site descriptive model. Groundwater flow in the crystalline rocks at Olkiluoto takes place predominantly in the<br />
void space of the interconnected fractures in the bedrock. Many of the hydraulic characteristics of flow through such a system can<br />
be represented by hydrogeological Discrete Fracture Network (DFN) models, since they capture some of the details of fracture<br />
geometry, size, connectivity and openings. The paper describes how field data is used to derive such models, ultimately for use in<br />
safety assessment.<br />
Surface based site investigations at Olkiluoto include 53 sub-vertical deep core drilled boreholes and 27 shallower sub-vertical<br />
boreholes. The characterisation of fractures is a key objective. Fracture geometrical data (fracture positions and orientations)<br />
are determined from drill core mapping and/or borehole ...<br />
4) SELF-DISPOSAL OPTION FOR HEAT-GENERATING WASTE (wP-59182)<br />
Michael Ojovan, University of Sheffield; Pavel Poluektov, Vladimir Kascheev, A.A. Bochvar’s VNIINM (UK/Russia)<br />
Self-descending heat generating capsules can be used for disposal of dangerous radioactive wastes in extremely deep layers of<br />
the Earth preventing any release of radionuclides into the biosphere. Self-disposal option for heat-generating radioactive waste such<br />
as spent fuel, high level reprocessing waste or spent sealed radioactive sources, known also as rock melting concept, was considered<br />
in the 70s as a viable alternative disposal option by both Department of Energy in the USA and Atomic Industry Ministry in<br />
the USSR. Self-disposal is currently reconsidered as a potential alternative route to existing options for solving the nuclear waste<br />
problem and is associated with the renaissance of nuclear industry. Self-disposal option utilises the heat generated by decaying<br />
radionuclides of radioactive waste inside a heavy and durable capsule to melt the rock on its way down. As the heat from radionuclides<br />
within the capsule partly melts the enclosing rock, the relatively low viscosity and density of the silicate melt allow capsule<br />
to be displaced upwards past the heavier capsule as it sinks. Eventually the melt cools and solidifies (e.g. vitrifies or crystallizes),<br />
sealing the route along which the capsule passed. Descending or self-disposal continues until enough heat is generated by radionuclides<br />
to provide partial ...<br />
5) NUMOS APPROACH FOR LONG-TERM SAFETY ASSESSMENT (wP-59404)<br />
Takeshi Ebashi, Kenichi Kaku, Katsuhiko Ishiguro, Nuclear Waste Management Organization of Japan (NUMO) (Japan)<br />
In Japan, the Act on <strong>Final</strong> Disposal of Specified Radioactive Waste specifies that the repository siting process shall consist of<br />
three stages. The Nuclear Waste Management Organization of Japan (NUMO) is responsible for geological disposal of vitrified<br />
high-level waste and some types of TRU waste. NUMO has chosen to implement a volunteer approach to siting.<br />
NUMO decided to prepare the 2010 Technical Report, which sets out three policies for ensuring safety. One of these is staged<br />
project implementation and decision-making based on iterative confirmation of safety. Based on this, NUMO will gradually integrate<br />
relevant interdisciplinary knowledge to build a safety case once a formal volunteer application is received that would allow<br />
site investigations to be initiated. The safety assessment takes the central role in multiple lines of reasoning and argumentation by<br />
providing a quantitative evaluation of long-term safety, a key aspect of which is uncertainty management.<br />
This paper presents NUMOs basic strategy for long-term safety assessment, based on the above policy.<br />
In concrete terms, safety assessment procedures are described in the context of the staged implementation programme, based<br />
on integration of knowledge obtained from site investigation/evaluation and engineering studies and reflection of the safety assessment<br />
results in the planning of ...<br />
6) MODELING APPROACHES FOR EVALUATING THE EFFECT OF HETEROGENEITY ON<br />
TWO-PHASE FLOW ASSOCIATED WITH THE MIGRATION OF WASTE GENERATED GAS<br />
FROM SF/HLW- AND L/ILW REPOSITORIES IN LOW-PERMEABILITY FORMATIONS (wP-59196)<br />
Alexandros Papafotiou, Rainer Senger, Intera Inc. Swiss Branch; Andrés Alcolea, TK Consult AG;<br />
William Lanyon, Fracture-Systems Ltd; John Ewing, Intera Inc. Swiss Branch (Switzerland/UK)<br />
Different low-permeability formations are considered as potential host rocks for Low / Intermediate Level waste (L/ILW) and<br />
spent fuel / high-level / long-lived intermediate-level waste (SF/HLW/ILW) in Switzerland. As part of a generic site evaluation<br />
process, emphasis is on the assessment of Mesozoic limestones, marls and claystones in six potential siting areas in Northern and<br />
Central Switzerland. An important aspect in the site evaluation process is the characterization of the low-permeability formations<br />
in terms of spatial variability of the relevant transport properties (porosity, permeability, clay content), as they may affect the migration<br />
of waste-generated gas from L/ILW and SF/HLW/ILW repositories.<br />
Numerical modeling studies are presented, aimed at quantifying the impact of spatial variability of rock properties on gas<br />
release through the host rock on a deca- to hectometer scale. For this purpose, 2-D models of an emplacement tunnel embedded in<br />
a low-permeability host rock are developed for both a sequence of limestones and marls with distinct lithological variability (Effingen<br />
Beds) and a claystone of moderate spatial variability (Opalinus Clay). For the Effingen Beds, a composite geological model is<br />
implemented, comprising stochastic representations of the different facies and the fracture systems. The facies model displays spatial<br />
variations in clay content, porosity ...<br />
96
Abstracts Session<br />
7) A NEW SAFETY CONCEPT FOR GEOLOGICAL DISPOSAL IN JAPAN (II) (wP-59357)<br />
Kazumi Kitayama, Nuclear Waste Management Organization of Japan (NUMO) (Japan)<br />
In a previous paper for ICEM2009 a new safety concept was proposed for the geological disposal program in Japan, which was<br />
a development of the conventional multi-barrier system concept that takes greater account of the actual behaviour in a deep geological<br />
environment. This paper describes progress of the study. In particular, it points out that geological disposal provides passive<br />
defence-in-depth safety functions based on geochemical equilibrium, and that natural analogues are effective in understanding the<br />
behaviour of engineered/natural barriers over hundreds of thousands of years and in further developing safety concepts. In addition,<br />
a long-term safety concept based on the realistic evolution of a geological disposal system can be explained to both the general<br />
public and experts in a straightforward and comprehensible manner.<br />
Detailed discussion of specific long-term behaviour of engineered and natural barriers, including possible interaction between<br />
barriers, will be reported in the paper.<br />
8) THERMO-HYDRO-MECHANICAL SIMULATION OF A HEATING AND HYDRATION<br />
EXPERIMENTAL STUDY (CHINA-MOCK-UP) IN UNSATURATED GMZ BENTONITE (wP-59212)<br />
Liang Chen, Ju Wang, Yuemiao Liu, Beijing Research Institute Of Uranium Geology;<br />
Federic Collin, University Of Liège; Jingli Xie, Beijing Research Institute Of Uranium Geology (China/Belgium)<br />
The preliminary repository concept for disposal of high level radioactive waste in China is a shaft-tunnel model, located in saturated<br />
zones in granite. The engineered barrier system (EBS) is composed of vitrified waste, canisters, buffer materials, backfill<br />
and seals. Unsaturated compacted bentonite is foreseen by lots of countries as a backfill and sealing material. At the present stage,<br />
the Gaomiaozi (GMZ) bentonite is considered as the candidate buffer and backfill material for the Chinese repository. In order to<br />
study the behavior of this material in coupled THMC conditions, a mock-up facility, named China-Mock-up, has been installed in<br />
Beijing Research Institute of Uranium Geology. The heater, which substitutes a loaded waste canister, is placed inside of the facility.<br />
To simulate the impact of groundwater, the water inflow of the barrier from outer surface is also possible. This paper presents<br />
a numerical study of the coupled THM behavior of China-mock-up test. In the paper, the basic physical characters of GMZ bentonite<br />
and experimental facility of China-mock-up test are firstly presented. Based on the experimental studies, the numerical simulation<br />
is realized by the program of LAGAMINE. In the simulation, the following physical phenomena are taken account: the<br />
transport of liquid (advection) and heat ...<br />
SESSION 33 — RECENT ADVANCES IN PROCESSING AND IMMBOLIZATION OF HLW,<br />
FISSLE MATERIAL AND TRANSUANIC (TRU) - PART 1 OF 2 (2.14)<br />
1) URANIUM METAL OXIDATION, GRINDING AND ENCAPSULATION IN BOROBOND:<br />
TRU WASTE MANAGEMENT (w/oP-59279)<br />
Kevin Cook, Larry Addington, Beth Utley, Boron Products (USA)<br />
Hydrogen generation mitigation for K Basin sludge was examined by encapsulation of uranium metal in BoroBond®, pre-oxidation<br />
of uranium metal with Fentons reagent and grinding of Densalloy SD170, an irradiated uranium metal surrogate. Encapsulation<br />
in BoroBond® resulted in pressure increase rates at 60°C ranging from 0.116 torr/h to 0.186 torr/h compared to 0.240 torr/h<br />
for a uranium metal in water standard. Samples cast with higher water content led to increased rates. A Fentons reagent system<br />
consisting of a simple reagent mix of FeSO4•7H2O, H2O2 and HCl effectively oxidized ¼ cubes of uranium metal in under four<br />
days at room temperature. Increased peroxide addition rate, increased FeSO4•7H2O concentration and low pH all increase the corrosion<br />
rate. Densalloy SD170 with an average particle size of 581 µm with 7.63 % of particles less than 90 µm was milled so that<br />
over 90 % of the Densalloy mass measured less than 90 µm in 6 hours of milling. Acceptable wear rates were seen on wear components<br />
that were from standard materials (Nitronic SS and 440SS).<br />
2) RESULTS OF INVESTIGATION OF HIGH LEVEL SOLID RADIOACTIVE WASTE<br />
FROM PITS NO1 AND NO2 AT THE GREMIKHA SITE (w/oP-59390)<br />
B.S. Stepennov, V.M. Afanasyev, A.Yu. Kazennov, N.V. Kartashev, A.V. Korolev, O.E. Kiknadze, D.V. Pavlov, Kurchatov<br />
Institute; V.V. Eremenko, FGUP SevRAO; G. Fady, CEA; Lucien Pillette-Cousin, Areva TA (Russia/France)<br />
One of the legacies of the Cold War period is the unsafe and uncontrolled storage of high level radioactive waste at the former<br />
soviet navy bases. At the former naval maintenance base of Gremikha in the North-West of Russia, it has been necessary to conduct<br />
characterization of high level waste in order to decide the best way to recover and condition it, with good radiation protection<br />
and safety conditions. France, represented by CEA, associated with AREVA TA as technical support, funded the studies performed<br />
by the Russian partners to define conditions of characterization of this high level waste that has been stored for tens of years in two<br />
pits, filled with water and containing sludge. The Russian Kurchatov Institute conducted the clarification of the water contained in<br />
the pit by removal of sludge using filtration techniques. Then, a 3D model of the content of the pits was realized including all<br />
objects identified after water clarification. Specific methods and technologies were used for that because the dose rates near some<br />
objects were as high as 400 Gy/h. Data obtained makes it possible now to choose the best option for the management of the identified<br />
high level solid radioactive waste. The paper presents the techniques used for clarification of water contained in the pits, the<br />
main results and the expected way forward to recover and condition this high level waste.<br />
97
Session 34 Abstracts<br />
3) PILOT TEST OF PRECIPITATION SETUP FOR DUST SUPRESSOR AND TRANSURANIC ELEMENTS<br />
REMOVAL FROM WASTEWATERS OF CHERNOBYL NUCLEAR POWER PLANT (w/oP-59256)<br />
Valentin Avramenko, Svetlana Bratskaya, Dmitry Marinin, Institute of Chemistry FEBRAS; Anatoliy Terzi,<br />
Mariya Yarmolyuk, Chernobyl Nuclear Power Plant (Russia/Ukraine)<br />
In this paper we report the results of pilot tests of flocculation/precipitation setup for dust-suppressor (DS) and transuranic elements<br />
(TRU) removal from wastewaters of Chernobyl Nuclear Power Plant (ChNPP), including those of the Object Shelter . Tests<br />
were performed on the pilot unit (PU), which included service tank, precipitation tank, and accumulation tank, 300 dm3 each, connected<br />
with pipelines with dosing and pumping equipment, and throttle valves providing controlled dosing, mixing, precipitation<br />
and mechanical filtration of radioactive wastewaters under different conditions. Three samples of the wastewaters drainage waters<br />
from the Object Shelter , combined drainage waters of Object Shelter and 3rd reactor unit of ChNPP, and evaporator concentrate<br />
from SVO unit of ChNPP were tested. The reagent compositions used in pilot tests were based on coagulant POLYPACS-30 LF<br />
(aluminum polyoxychloride), synthetic cationic flocculants Besfloc K6634, K510CA, K6732 («Kolon Life Science, Inc», South<br />
Korea) varying in molecular weight and charge density, and natural cationic flocculant «Chitofloc» (Institute of Chemistry<br />
FEBRAS, Russia). The following wastewater parameters were controlled during the pilot tests: pH, dry residue, oxygen consumption,<br />
total alpha- and beta-activity, isotope composition, optical density and DS content.<br />
It was shown that wastewaters with DS content of 200-300 mg/L could be effectively…<br />
4) SEPARATION PROCESSES FOR THE PRETREATMENT OF HIGH-LEVEL NUCLEAR<br />
WASTES AT THE SAVANNAH RIVER SITE (w/oP-59291)<br />
David Hobbs, Aiken, Thomas Peters, Kathryn Taylor-Pashow, Fernando Fondeur, Charles Nash, Samuel Fink,<br />
David Herman, Savannah River National Laboratory (SRNL) (USA) Presentation by: Jim Marra, US DOE (USA)<br />
Separation methods for the pretreatment of the high-level nuclear wastes (HLW) at the Savannah River Site (SRS) include the<br />
Caustic Side Solvent Extraction (CSSX) process for cesium and adsorption/ion exchange for the removal of cesium, strontium and<br />
alpha-emitting actinides. The CSSX process uses a calixarene extractant in combination with phase modifiers in a hydrocarbon<br />
diluent. Monosodium titanate (MST), a hydrous metal oxide, is the baseline material for the removal of strontium and alpha-emitting<br />
radionuclides (principally Pu-238, Pu-239, Pu-240 and Np-237). Two pretreatment facilities, the Modular Caustic Side Solvent<br />
Extraction Unit (MCU) and the Actinide Removal Process (ARP) facility began radioactive operations at SRS in 2008.<br />
Together these facilities can treat approximately 4 million liters of waste per year. The same separation processes are also planned<br />
for the much larger Salt Waste Processing Facility (SWPF). The SWPF, which has a design throughput of about 27 million liters<br />
per year, is under construction and scheduled to begin radioactive operations in 2014.<br />
Current R&D activities for the CSSX process are focused on implementing a new solvent system and stripping flowsheet that<br />
offers enhanced extraction and stripping of cesium. This next generation solvent system features a different calixarene extractant,<br />
uses caustic instead of nitric…<br />
SESSION 34 — URANIUM SITES, ER ISSUES, SITE CHARACTERIZATION<br />
AND MONITORING - PART 2 OF 2 (4.12) (4-6)<br />
1) SAMPLING IN DECOMMISSIONING: CETAMA SEMINAR AND INTERNATIONAL OVERVIEW (w/oP-59209)<br />
Guy Granier, Daniele Roudil, CEA MARCOULE; Didier Dubot, CEA/FAR/USLT/SPRE/SAS (France)<br />
The quality of measurement is crucial for the safety of nuclear facilities and is a primary requirement for the characterization<br />
of nuclear materials, fissile material monitoring and accountancy.<br />
The Commission for the Establishment of Analysis Methods (CETAMA) is a unit of the French Alternative Energies and Atomic<br />
Energy Commission (CEA) set up to improve the quality of analysis and measurement results, in the nuclear field, by proposing<br />
suitable scientific and technical developments:<br />
• Preparation and/or certification or reference materials;<br />
• Organization of interlaboratory comparisons to assess the quality of the results and to validate analysis methods<br />
• Published methods and reference documents validated by laboratory experiment<br />
• Organization of workshops to share the reporting of experience among analysts<br />
To ensure, at each level of its exploitation, a control of nuclear material dissemination is a main priority of nuclear industry in<br />
France. Analysis is the main tool of supervision to follow this goal.<br />
By the choice of adapted tracers, with definite frequencies the analysis allows a control and a follow-up of the nuclear operation<br />
of the installations.<br />
For more than 50 years of uninterrupted evolution this industry developed the comprehensive view about different aspects,<br />
civil, military, production of energy or medical…<br />
2) FOAM NOVEL DELIVERY TECHNOLOGY FOR REMEDIATION<br />
OF VADOSE ZONE ENVIRONMENTS (wP-59019)<br />
Dawn Wellman, Danielle P Jansik, Shas Mattigod, Lirong Zhong, Pacific Northwest National Laboratory;<br />
Yuxin Wu, Lawrence Berkeley National Lab; Martin Foote, MSE Technology Applications;<br />
Z. F. (Fred) Zhang, Pacific Northwest National Laboratory; Susan Hubbard, Lawrence Berkeley National Lab (USA)<br />
Deep vadose zone environments can be a primary source and pathway for contaminant migration to groundwater. These environments<br />
present unique characterization and remediation challenges that necessitate scrutiny and research. The thickness, depth,<br />
and intricacies of the deep vadose zone, combined with a lack of understanding of the key subsurface processes (e.g., biogeochemical<br />
and hydrologic) affecting contaminant migration, make it difficult to create validated conceptual and predictive models of subsurface<br />
flow dynamics and contaminant behavior across multiple scales. These factors also make it difficult to design and deploy<br />
sustainable remedial approaches and monitor long-term contaminant behavior after remedial actions.<br />
98
Abstracts Session 35<br />
Functionally, the methods for addressing contamination must remove and/or reduce transport of contaminants. This problem<br />
is particularly challenging in the arid western United States where the vadose zone is hundreds of feet thick, rendering transitional<br />
excavation methods exceedingly costly and ineffective. Delivery of remedial amendments is one of the most challenging and critical<br />
aspects for all remedy-based approaches. The conventional approach for delivery is through injection of aqueous remedial solutions.<br />
However, heterogeneous deep vadose zone environments present hydrologic and geochemical challenges which limit the<br />
effectiveness. Because the flow of solution infiltration is dominantly controlled by gravity and suction, injected liquid preferentially<br />
percolates…<br />
3) MOBILITY OF RADIUM FROM PYRITIC URANIUM MINE TAILINGS UNDER<br />
SUB-AQUEOUS DISPOSAL CONDITIONS (wP-59283)<br />
Nand Dave, Mining and Mineral Sciences Laboratories Canada (Canada)<br />
All uranium mines in the Elliot Lake uranium mining district of north-central Ontario, Canada, have been closed due to low<br />
ore grade and prevailing market conditions. A majority of the waste management facilities have been rehabilitated and decommissioned<br />
with in-situ shallow water covers to minimize sulphide oxidation, and hence acid generation and release of metal enriched<br />
effluents.<br />
Laboratory lysimeter investigations were undertaken to evaluate the leaching characteristics and mobility of Ra-226 and other<br />
heavy metals (U, Th and Pb) from pyritic uranium mine tailings under sub-aqueous disposal conditions for assessing the long-term<br />
radiological stability of such waste repositories. The experiments were conducted using three types of un-oxidized tailings: coarse,<br />
fine and gypsum depleted mill total tailings. Shallow water covers of depth ~ 0. 3 m were established using natural lake water. The<br />
leaching characteristics of radium and other major and trace metals were determined by monitoring both surface and pore water<br />
qualities as a function of time.<br />
The results showed that Ra-226 is leached from surface of the submerged tailings and released to both surface water and shallow<br />
zone pore water during initial low sulphate ion concentration of the surface water cover in all three cases. The release of Ra-<br />
226…<br />
4) REMEDIATION PROJECT PLANNING AT THE URANIUM PRODUCTION LEGACY SITES.<br />
LESSON LEARNED FROM THE BEST INTERNATIONAL PRACTICE AND CHALLENGES<br />
FOR DEVELOPING COUNTRIES (wP-59043)<br />
Oleg Voitsekhovych, Ukrainian Hydrometeorological Institute (Ukraine)<br />
The former Soviet Union countries such as Kazakhstan, Kyrgyzstan, Russia, Tajikistan, Uzbekistan and Ukraine, where uranium<br />
production legacy sites are located (such as mines, waste rock piles, pits, chemical and hydrometallurgical plants, tailing<br />
dumps, etc.) are currently facing the challenge of making these objects environmentally safe. These countries share a common history<br />
of the uranium mining and milling industry, similar regulatory shortcomings and uncertainties regarding the strategy justification<br />
for such remediation projects. They also have to deal with scarcity of financial resources for long-term remediation programmes,<br />
and lack of experience with planning and management of environmental remediation projects at former uranium production<br />
sites.<br />
In the recent years, IAEA-supported programmes of international technical co-operation (the projects RER/0986 and<br />
RER/3010) were advancing actively, as well as those sponsored by the UNDP, EurAsEC and others, all aiming to assist with the<br />
preparedness and performance of future remediation projects. As demonstrated by analysis, effectiveness of the many programmes<br />
largely depends on the nations’ level of preparedness to carry out remediation projects in accordance with the international standards.<br />
The lessons learned from analyses of the different type of projects, which were already implemented or which are still in plan<br />
in different countries and in particular…<br />
5) CLOSE-OUT OF OPEN PIT AND WASTE ROCK PILES OF DAXIN URANIUM MINE OF CHINA (wP-59073)<br />
Lechang Xu, Changshun Ren, Min Shi, Liaoning Xueli Zhang,<br />
Jie Gao, Beijing Research Institute of Chemical Engineering and Metallurgy, CNNC (China)<br />
Daxin Uranium Mine is an small open pit mine. Its contaminated facilities include open pit 87620m2 , East waste rock pile<br />
71710m2 , west waste rock pile 57828m2 , ore transfer station and industrial fields 9370m2 , building and structure 26600m2 , equipment<br />
246 pieces, plastic conduit 3000m. steel conduit 2500m2 and road for transporting ores 1020m. The integrated decommissioning<br />
programmes are presented: uranium extraction, slope stabilization, clear-up, backfill, reshape, covering, re-vegetation, dismantlement/demolishment,<br />
decontamination, re-smelting, waste water treatment.<br />
SESSION 35 — (MERGED WITH SESSION 34)<br />
SESSION 36 — RADIUM REMEDIATION: HISTORICAL PERSPECTIVES<br />
AND CURRENT CIRCUMSTANCES - PART 1 OF 3 (4.11)<br />
1) RADIUM DIAGNOSIS CAMPAIGN (wP-59327)<br />
Florence Gabillaud-Poillion, Autorité de Sûreté Nucléaire (France)<br />
In line with the approaches already adopted in France during the 90s on various sites where research and/or radium-extraction<br />
activities were mostly conducted in the past, the French public authorities wish from now on to pursue their prevention and siterehabilitation<br />
approach inherited from the French craftsman and medical sectors that used that radioelement.<br />
As a matter of fact, radium has been in use in several medical activities, notably in the initial methods of cancer therapy. Similarly,<br />
it was also used in some craftsman activities, such as the clock industry, for its radioluminescent properties, the fabrication<br />
of lightning conductors or cosmetics until the 60s. Those activities have generated various traces of pollution that have remained<br />
today.<br />
99
Session 36 Abstracts<br />
On the basis of the different inventories of industrial sites where radium may have been held or used, and notably the inventory<br />
updated by the French Institute for Radiation Protection and Nuclear Safety (Institut de radioprotection et de sûreté nucléaire<br />
IRSN) in 2007 at the request of the French Nuclear Safety Authority (Autorité de sûreté nucléaire ASN), French State services<br />
have potentially identified 134 sites that hosted radium-related activities in France. The radiological status of those sites is either<br />
unknown or very partially…<br />
2) ANDRA’S REMEDIATION MISSIONS (w/oP-59210)<br />
Patrick Poiret, Eric Lanes, Andra (France)<br />
For many years now, the French National Radioactive Waste Management Agency (Agence nationale pour la gestion des<br />
déchets radioactifs Andra) has been cleaning up several sites contaminated with radioactivity, bearing in mind that all such remediation<br />
missions share the unique peculiarity of being performed entirely outside the nuclear-power-generation field.<br />
Thanks to the 2006 Planning Act and the new corporate circular in the legal field, to the implementation of the CNAR for<br />
organisational purposes, to the public technical subsidy for dedicated storage facilities and the disposal facility for VLL waste (Centre<br />
TFA) from a financial standpoint, Andras new structure is now in place to ensure a proactive approach to manage the environmental<br />
liabilities arising from the sites polluted by radioactive materials, which, although scarce in number, each confront us with<br />
a specific challenge.<br />
3) URANIUM MILL TAILINGS REMEDIATION IN THE USA. A HISTORY AND LESSONS LEARNED (w/oP-59407)<br />
Steve Rima, AMEC (USA)<br />
Since the 1940s uranium ores have been processed at various locations in the United States to extract and produce uranium and<br />
other concentrated materials, first for government (weapons) research and production, and then for nuclear power production. The<br />
tailings residue from the uranium milling process contained radioactive (primarily Ra-226) and hazardous chemicals. Large volumes<br />
of tailings were produced during the milling process. In the early history of this process the tailings were not recognized as<br />
hazardous and were released to the general public for a wide variety of uses, resulting in significant spread of contamination in the<br />
vicinity of many operating mills.<br />
In the late 1960s and early 1970s laws were enacted at the state and federal level to begin to deal with the legacy of this contamination.<br />
Over the course of the next several decades various regulatory agencies were responsible for remediating these sites.<br />
Different approaches were used, different end points and definitions of clean were used, and very large sums of public funding were<br />
spent on remediating these sites. Rarely was the cost commensurate with the risk reduction obtained through remediation.<br />
This paper will present an overview of the history of the uranium mill tailings regulatory and remediation program in the United<br />
States, the cost of the program compared to risk reduction, successes and failures, and important lessons learned that should be<br />
applied to future efforts in this area.<br />
4) REMEDIATION OF CANADA’S HISTORIC HAUL ROUTE FOR RADIUM AND<br />
URANIUM ORES: THE NORTHERN TRANSPORTATION ROUTE (wP-59303)<br />
Robert Brian Geddes, Chris Wenzel, AMEC; Michael Owen,<br />
Mark J. Gardiner, AECL; Julie Brown, Natural Resources Canada’s (Canada)<br />
Established in the 1930s, the Northern Transportation Route (NTR) served to transport pitchblende ore 2,200km from the Port<br />
Radium Mine in Canadas Northwest Territories to Fort McMurray in Alberta. From there, the ore was shipped 3,000km by rail to<br />
the town of Port Hope, Ontario where it was refined for its radium content and used for medical purposes. Later, refinement<br />
focussed on uranium content.<br />
The corridor of lakes, rivers, portages and roads that made up the NTR included a number of transfer points, where ore was<br />
unloaded and transferred to other barges or trucks. Ore was occasionally spilled during these transfer operations and, in some cases,<br />
subsequently distributed over larger areas as properties were re-developed or modified. In addition, relatively small volumes of ore<br />
were sometimes transported by air to the south.<br />
Since 1992, the Low-Level Radioactive Waste Management Office (LLRWMO) has conducted surveys to identify and characterize<br />
spill sites along the NTR where soils exhibit elevated concentrations of uranium, radium and/or arsenic. In addition to significant<br />
areas of impact in Fort McMurray, contamination along the NTR was centred in the Sahtu region near Great Bear Lake and<br />
along the southern part of the Slave River. Early radiological investigations found…<br />
SESSION 37 — YOUNG GENERATION NETWORK (YGN) AND<br />
PROFESSIONAL DEVELOPMENT PROGRAMS (5.16)<br />
1) THE REESTABLISHMENT OF RADIOCHEMISTRY ACADEMIC<br />
PROGRAMS IN THE UNITED STATES (w/oP-59025)<br />
Craig Williamson, South Carolina Universities Research and Education Foundation (USA)<br />
Despite its importance in national security, medicine, energy, and in waste management radiochemistry education in the United<br />
States has gone through two lost decades. In the 1970s ten to fifteen universities were granting between thirty (30) and forty (40)<br />
doctoral degrees a year. By the 1980s those numbers had declined to twenty (20) and thirty (30) a year, by the 1990s the numbers<br />
had again decreased to below fifteen (15) Ph.D.s a year. In the year 2000, the data shows that only 5 Ph.D.s in radiochemistry were<br />
awarded. The causes for this decline is directly attributed to the lack of federal support for an academic discipline that for the most<br />
part depends on federal funding.<br />
In 2011, it is expected that over thirty (30) doctoral degrees in radiochemistry will be conferred. The turn around in radiochemistry<br />
education in the United States can be directly attributed to the support provided by the U.S. Departments of Energy, Defense<br />
and Homeland Security. In addition, support has come from the U.S. Nuclear Regulatory Commission and from the National<br />
Nuclear Security Administration. The form of this support has been extensive from proposed undergraduate research programs,<br />
scholarships, graduate fellowships, junior faculty awards, curriculum awards, and grants…<br />
100
Abstracts Session 38<br />
2) PLANNING FOR DECOMMISSIONING OF NUCLEAR FACILITIES -<br />
THE VIEWS OF YOUNGER STAKEHOLDERS (wP-59222)<br />
Staffan Lindskog, Swedísh Radiation Safety Authority;<br />
Bea Labor, Badania Dydaktycne Project 2010 (Sweden/Poland) (<strong>Final</strong> paper received and Copyrights pending)<br />
Title: Nuclear as a semi-sustainable energy source the views of younger stakeholders<br />
It is planned that many nuclear facilities will be decommissioned in the near future. This challenge includes certified repositories<br />
for LLW and ILW, procedures for classification and free release, systems for transportation, planning activities, and liaison with<br />
the public. The last item can have a substantial impact on the efficiency of decommissioning projects. Insufficient dialogue with<br />
various stakeholder groups can be a factor that drives costs, whilst appropriate programs, means and environments for communication<br />
and knowledge transfer may facilitate the establishment of contemporary and comprehensive bases for decisions and thereby<br />
also enhance the possibility for consensus and thereby achieve feasible and sustainable solutions. The programs thus decided for<br />
the decommissioning of nuclear facilities and the management of the nuclear waste must then be communicated openly and constitute<br />
an integral part of the stakeholder related activities.<br />
The nuclear renaissance implies as well as calls for newer platforms for communications with the stakeholders. This communication<br />
must include how compliance with the Polluter Pays Principle (PPP) (and also preferably the Extended Polluter Responsibility,<br />
EPR) is to be achieved, i. e. how the generation harvesting the benefits from nuclear electricity will…<br />
3) GRADUATE OR APPRENTICE? HOW NUCLEAR TRAINING PROVISION HAS CHANGED<br />
THE SHAPE OF THE NUCLEAR EMPLOYMENT MARKET (w/oP- 59415)<br />
Corhyn Parr, Nuclear Enterprise (UK)<br />
ABSTRACT NOT AVAILABLE<br />
4) NUCLEAR KNOWLEDGE DEVELOPMENT - OVERVIEW OF THE ACTIVITIES<br />
PROPOSED BY SFEN YOUNG GENERATION (SFEN-JG)<br />
Guillaume Vaast, SGN–Pierrelatte (France)<br />
ABSTRACT NOT AVAILABLE<br />
SESSION 38 — MEETING: YOUNG GENERATION NETWORK (YGN)<br />
AND PROFESSIONAL DEVELOPMENT PROGRAMS (5.17)<br />
ABSTRACT NOT AVAILABLE<br />
SESSION 39A — POSTER SESSION: FACILITY DECONTAMINATION AND DECOMMISSIONING<br />
A-1) USE OF HIGHLY PRESURIZED LIQUID NITROGEN TECHNOLOGY FOR CONCRETE<br />
SCABBLING APPLICATION AT SICN NUCLEAR FACILITIY (wP-59282)<br />
Fabrice Moggia, Claire-Emilie Vaudey, Thierry Varet, Valérie Toulemonde, AREVA;<br />
Frédéric Richard, Air Liquide CTAS; Gary Anderson, Nitrocision; Frédérique Damerval, AREVA (France/USA)<br />
Dismantling and decommissioning (D&D) operations of nuclear site facilities usually involve the implementation of a large<br />
number of technologies. These technologies are mostly dedicated to decontamination, cutting and concrete scabbling operations.<br />
Technologies used for example for concrete scabbling are: disk sander, bush hammer, water jet, planer & Such mechanicals processes<br />
proved to work since facilities are being decommissioned; however as larger projects are foreseen, the capability of such applications<br />
to fulfill the requirement in term of economics, techniques and environment/social remains uncertain. Indeed, the efficiency<br />
and the speed rate remains low, many operators are required to operate, implying a high dosimetry, the working conditions are<br />
strenuous and finally the operations could last several years for large surfaces&<br />
For all these reasons, it seems necessary to search for new technologies, which would bring sustainability to the D&D operations<br />
while carrying a higher standard in terms of safety, easiness and economic value.<br />
The Nitrojet technology is a process able to produce liquid nitrogen at low temperature and very high pressure (up to 4000<br />
bar). Liquid nitrogen is collected from a tank to be pressurized in a specific skid. The nitrogen stream can then be applied on the<br />
substrate<br />
The use of this new…<br />
A-2) METHODOLOGY OF EXTERNAL EXPOSURE CALCULATION FOR REUSE OF<br />
CONDITIONAL RELEASED MATERIALS FROM DECOMMISSIONING (wP-59138)<br />
Frantisek Ondra, Marek Vaako, DECOM, a.s.; Vladimir Necas, Slovak University of Technology (Slovakia)<br />
Conditional release of materials is a part of nuclear installation decommissioning that can significantly influenced radioactive<br />
waste management, radioactive waste repository capacity usage as well as total decommissioning cost. For performance of conditional<br />
released materials scenarios it is needed to determine radiological, material, organizational and other conditions for conditionally<br />
released materials reuse to not breach exposure limits for staff and public during scenarios life cycle (preparation, construction<br />
and operation of scenario). The article presents a methodology for determination of above mentioned conditions to ensure that<br />
staff and public exposure does not breach the limits. The methodology comprises a proposal of following conditions in the view of<br />
staff and public exposure:<br />
• radionuclide limit concentration of conditionally released materials for specific scenarios and nuclide vectors,<br />
• specific deployment of conditionally released materials eventually shielding materials, staff and public during the scenarios<br />
life cycle,<br />
101
Session 39 Abstracts<br />
“ organizational measures concerning time of staffs or publics stay in the vicinity on conditionally released materials for<br />
individual performed scenarios and nuclide vectors.<br />
The article further describes VISIPLAN 3D ALARA calculation planning software tool, having been used for calculation of<br />
staffs and publics external exposure for individual scenarios. Several other parallel papers proposed for ICEM 11 are presenting<br />
selected details of the project.<br />
A-3) UNCERTAINTY ANALYSIS OF ACTIVITY MEASUREMENT OF NEW MONITORING SYSTEM<br />
FOR FREE-RELEASE FOR NPP A-1 DECOMMISSIONING, SLOVAKIA (wP-59244)<br />
Alojz Slaninka, VUJE, a.s./ Slovak University of Technology in Bratislava; Ondrej Slávik, VUJE, a.s.;<br />
Vladimir Necas, Slovak University of Technology (Slovakia)<br />
Within 2nd stage of decommissioning project of NPP A-1 in Slovakia it is necessary to decontaminate, monitor and if possible<br />
to free release large amounts of contaminated materials, mainly contaminated soil and concrete debris (thousands of tons). Their<br />
contamination is caused by dominant 137Cs (33 years after shutdown) that emits 661.65 keV gamma ray that can be easily detected<br />
by scintillation or semiconductor detectors. In this connection a new free release monitoring post with a large volume 600 L container<br />
counting geometry was designed and developed. The monitoring system is based on a pair of electrically cooled semiconductor<br />
HPGe detectors that are placed into a modifiable vertical or horizontal pair of lead collimators. The detectors are equipped<br />
with a Canberra Packard gammaspectrometry chain including proper characterised HPGe detectors type GC 3020. The vertical<br />
arrangement of the collimator ensures monitoring of materials in 200 l rotating drums. The horizontal one ensures monitoring of<br />
the one side of a 600 l rectangular container. The monitoring system is integrated with an industrial scale for determination of massic<br />
activities of measured materials and in addition by a rotating table in the case of 200 l drums monitoring. Full-energy peak detection<br />
efficiency polynomial curves…<br />
A-4) LASER REMOVAL OF CONTAMINANTS ON THE METAL SURFACE (wP-59343)<br />
Hui Jun Won, Jei Kwon Moon, Sun Hee Jung, Chong Hun Jung,<br />
Kune Woo Lee, Korea Atomic Energy Research Institute;<br />
Byung -Sun Choi, Korea Atomic Energy Research Institute (Korea)<br />
A Q-switched Nd:YAG laser with a 532 nm and 450 mJ/pulse was employed to study the decontamination characteristics of<br />
Type 304 stainless steel specimens and aluminum specimens artificially contaminated with CsNO3 , Co(NH4 ) 2 (SO4 )2, Eu2O3 and<br />
CeO2 , respectively. The relative atomic molar ratio of the contaminants on metal surface before and after laser irradiation was determined<br />
by EPMA. The morphology of specimen surface was examined by SEM. The optimum number of laser shots and the laser<br />
fluence for the system were determined. More than 98 % of CsNO3 , Co(NH4 ) 2 (SO4 )2, Eu2O3 on Type 304 stainless steel specimens<br />
could be removed by the circular type laser beam within the 16 laser shots at 13.3 J/cm2 and 10 Hz. The removal of contaminants<br />
on aluminum surface, however, was found to be more difficult by laser. Comparative study on the removal characteristics<br />
between the circular type laser beam and the string type laser beam was also performed. The variation of laser removal performance<br />
on the contaminants was investigated by changing the irradiation angle.<br />
A-5) INFLUENCE OF THE CONDITIONAL RELEASE OF THE MATERIALS WITH VERY<br />
LOW LEVEL OF RADIOACTIVITY ON THE ENVIRONMENT (wP -59132)<br />
Slavka Prvakova, University of Economics in Bratislava; Adela Mrskova, DECOM, A. S.;<br />
Jozef Pritrsky, DECOM (Slovakia)<br />
Significant amount of solid materials (metals, non-metals, building structures) that could be contaminated or activated is produced<br />
during operation and especially decommissioning of nuclear power plants. Considerable fraction of these materials has level<br />
of radioactivity close to the radiological limits allowing its safe release into the environment thereby could be potentially recycled<br />
within the special constructions, as for example tunnels, roads or bridges. If the requirements of legislation on the radiological limits<br />
for handling such material and long term safety of the constructions are fulfilled, contaminated material can be released in the<br />
form of recycled concrete, remelted steel, etc.<br />
The paper presents implementation of the IAEA and EC recommendations into the form of detailed analytical approaches with<br />
the aim to develop integrated scenarios and to analyse long-term influence of the conditional release of the material with very low<br />
level of radioactivity on the environment. Further, an estimation of the key input parameters characteristic for the specific conditions<br />
of Slovak case in order to fulfil the radiological limits according to the Slovak legislation is included. Analysed integrated scenarios<br />
represent surface or underground civil construction with radionuclides released directly into the geosphere and transported<br />
by a groundwater flow into the biosphere. The migration of radionuclides is modelled in the near-surface conditions with the advection<br />
as a dominant transport mechanism. Computer code GoldSim is used to evaluate the long-term safety assessment of the conditionally<br />
released material on the environment.<br />
A-6) CONDITIONAL RELEASE OF STEEL FROM DECOMMISSIONING<br />
IN A FORM OF REINFORCED CONCRETE (wP -59058)<br />
Jozef Pritrsky, DECOM; Miroslav Brodnan, University of Zilina;<br />
Vladimir Necas, Slovak University of Technology (Slovakia)<br />
The paper deals with the conditional release of low-level radioactive steel from decommissioning in a form of reinforced concrete.<br />
The main goal was to determine limits for radionuclides concentration and calculate the annual dose for a member of a critical<br />
group of public, which should not exceed 0.01 mSv/year (according to IAEA Safety Guide RS-G-1.7). Corrosion is the principle<br />
mechanism of radionuclides release in this case, therefore effort was devoted to assess the time-dependent rate of steel reinforcement<br />
corrosion. It was assumed, that concrete is initially highly alkaline (with pH of 12 to 13) because of hydration products<br />
such as calcium hydroxide, which keeps the steel surface passive and protected from corrosion. However, carbonic acid resulting<br />
from carbon dioxide and water in the atmosphere can react with these products to produce calcium carbonate. This process is<br />
102
Abstracts Session 39<br />
referred to as a -carbonation and leads after a period of time to significant reduction of the alkalinity (to pH as low as 8.5) followed<br />
by destruction of passive layer and starting corrosion of the embedded steel. The analytical principles and a set of input data have<br />
been implemented into a mathematical model developed by means of GoldSim software. The paper presents the results of mathematical<br />
simulation of corrosion precess, which are compared with real measured values.<br />
A-7) DECOMMISSIONING OF THE UF6 SPHERE (w/oP -59200)<br />
Sylvain Chevassu, ONET Technologies - ONECTRA (France)<br />
Technically, ONECTRA has started with the decontamination, under containment, with a teleoperated arm. The complete operations<br />
of internal cleaning and radiological controls will be operated with this arm. The internal particles are carried out applying<br />
two distinct processes: first, a mechanical decontamination process (brushing/aspiration), followed by a chemical decontamination<br />
process (pulverization of an acid solution). At the end of internal cleaning, the lower part of Sphere will be cut under containment<br />
with mechanical-cutting tools. An internal radiological map will validate that the final decontamination objectives have been<br />
reached. The final validation of the Spheres internal cleaning will be delivered through the agreement of the safety authority, mainly<br />
based at the end of the operation report.<br />
This safety authoritys agreement will allow the final Spheres dismantling sequence, consisting in outdoor cutting operations<br />
with no containment using oxy-gas cutting processes. The last step consists in building a cover slab under the Sphere. This last step<br />
requires a second agreement from the safety authority.<br />
A-8) DEVELOPMENT OF NUCLEAR FACILITIES PIPING CLEANING<br />
SYSTEM USING MICROBUBBLE (w/oP-59070)<br />
Jongseon Jeon, SangChul Lee, Byoungsub Han, Enesys Co., LTD.;<br />
HakSoo Kim, Nuclear Engineering & Technology Institute; Wisoo Kim, Enesys Co., Ltd. (Korea)<br />
It removes radioactive sludge and corrosion products deposited on the inner walls of the pipes and valves in replacement or<br />
decommission, upon termination of life time, of nuclear power plant or nuclear facility. It lowers a cost of waste treatments taking<br />
advantage of a reduction of quantity of radioactive wastes by treating in classification of the radioactive wastes whose activities are<br />
lower than legal standards.<br />
The cleaning or decontamination methods developed until now have induced a damage on systems while being operated. A<br />
decontamination has been restrained if it was difficult to access physically. We are in development of the cleaning technique for<br />
pipelines by utilizing micro-bubbles in order to improve an efficiency and to prevent from any damage of systems. It aims to conduct<br />
a decontamination for spaces difficult to access there by applying cavitation phenomenon that is generated in collapse of<br />
micro-bubbles. In order to improve an efficiency of the micro-bubble device, the experimental conditions suitable to decontamination<br />
have been established and the auxiliary equipments have been added. The generation conditions and characteristics of microbubbles<br />
have been demonstrated by adjusting pHs and temperatures of cleaning solution. A decontamination effect has been confirmed<br />
by adding up an electrolytic method and ozone into micro-bubbles.<br />
A-9) A MATRIX INVERSION METHOD FOR GAMMA-SOURCE MAPPING<br />
FROM GAMMA COUNT DATA (wP -59082)<br />
Richard Bull, Claire Burgess, Ian Adsley, Nuvia Limited (UK)<br />
Gamma ray counting is often used to survey the distribution of active waste material in various locations. Ideally the output<br />
from such surveys would be a map of the activity of the waste. In this paper a simple matrix inversion method is presented. This<br />
allows an array of gamma-count data to be converted to an array of source activities.<br />
For each survey area the response matrix is computed. The elements in this matrix are calculated using a gamma shielding code<br />
such as MicroShield (1). This matrix links the activity array to the count array. The activity array is then obtained via numerical<br />
matrix inversion. The method was tested on artificially created arrays of count data onto which statistical noise had been added.<br />
The method was able to reproduce, quite faithfully, the original activity distribution used to generate the dataset.<br />
The method has been applied to a number of practical cases, including the distribution of activated objects in a hot cell and to<br />
activated nimonic springs amongst fuel-element debris in vaults at a nuclear plant.<br />
Reference<br />
1) MicroShield, Version 8, Grove Software, 2009.<br />
A-10) DECOMMISSIONING ACTIVITIES FOR SALASPILS RESEARCH REACTOR (wP -59055)<br />
Andris Abramenkovs, Latvian Environment, Geology and Meteorology Centre;<br />
Jazeps Malnacs, State Environmental Service (Latvia)<br />
In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor (SRR). The reactor is out of operation<br />
since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und<br />
Umwelttechnik GmbH at 1998-1999. The Latvian government decided to start the direct dismantling to green field” in October 26,<br />
1999. The upgrade of decommissioning and dismantling plan was performed in 2003-2004 years, which change the main goal of<br />
decommissioning to the brown field.<br />
The paper deals with the SRR decommissioning experience during 1999-2010. The main decommissioning stages are discussed<br />
including spent fuel and radioactive wastes management. The legal aspects and procedures for decommissioning of SRR are<br />
described in the paper. It was found, that the involvement of stakeholders at the early stages significantly promotes the decommissioning<br />
of nuclear facility.<br />
Radioactive waste managements main efforts were devoted to collecting and conditioning of historical radioactive wastes from<br />
different storages outside and inside of reactor hall. All radioactive materials (more than 96 tons) were conditioned in concrete containers<br />
for disposal in the radioactive wastes repository Radons at Baldone site. The dismantling of contaminated and activated<br />
components of SRR systems is discussed in paper. The cementation of dismantled radioactive wastes in concrete containers is discussed.<br />
103
Session 39 Abstracts<br />
A-11) TECHNICAL JUSTIFICATION & CHOICE FOR REMEDIATION METHODS (wP -59398)<br />
Mark Morton, Janaka Jayamaha, WorleyParsons (USA)<br />
When out of normal material or very high activity is encountered in a D&D project, special considerations are needed. As the<br />
source term increases, the level of attention to planning, project cost and risk management must increase as well. WorleyParsons<br />
Polestar (WPP) is engaged in defining and documenting (with follow on project design expected) the remediation methods to<br />
remove contaminated soils discovered under a hot cell. Soil dose rates have been measured in the 7000 to 8900 Rem/hour, with<br />
radionuclide mix to be defined in mid to late summer 2011 from samples drawn in June 2011. The scope of the current project is<br />
to search remedial techniques and removal methods and define a set of possible alternatives. These alternatives will be screened<br />
by WPP and client expert panel using a WPP defined process to short list the project alternatives. Transparency and un-biased<br />
choice of actions is key to owner and public confidence in the process and the choice of the ultimate path forward.<br />
The poster will show Phase 1- how possible means and methods were first identified, catalogued and the initial screening of<br />
the means and methods (technologies). The remaining means and methods are being mixed to form an alternative…<br />
A-12) NEW GENERATION OF DIAMOND TOOLINGS FOR FACILITATING<br />
DECOMMISSIONING OPERATIONS (wP-59396)<br />
Claude Besson, Erico Mariotti, Alexandre Mouysset, Lorenz Zur Nedden,<br />
Bernard Delannay, Carbodiam (France/Belgium)<br />
Diamond tools are well proven cutting, drilling and grinding technologies in many applications but need to be specifically optimized<br />
and adapted for the complex and varied structures of nuclear power plant in view of decontamination and decommissioning.<br />
The proper development and use of diamond tools in these extreme and complex conditions can only be achieved thanks to the<br />
combined talent of experienced nuclear plant contractors, engineers, technicians, operators of diamond tools, and the use of specialized<br />
equipment.<br />
This present paper is an overview of the possible applications of diamond tools in the different operations of Nuclear Decommissioning<br />
and Decontamination.<br />
KEY DIAMOND TOOL APPLICATIONS for Decommissioning and Decontamination of Nuclear Power Plant:<br />
1) Wet/dry concrete wall sawing (with remote control system)<br />
2) Wet/dry wire cutting of concrete<br />
3) Wet/dry wire sawing of metal<br />
4) Wet/dry core drilling<br />
5) Grinding and leveling for surface preparation including all edges<br />
6) Scraping for removing bituminous or neoprene glues and all kinds of coatings<br />
7) Shaving for horizontal and vertical surfaces and ceilings<br />
Each situation requires a detailed feasibility study and engineering report to select the optimal work method and answer concerns<br />
about safety, time to completion and waste volume...<br />
A-13) POMPE SECONDAIRE (w/oP -59413)<br />
Anne Durand, CEA (France)<br />
La caractérisation globale du composant a permis de classer entièrement la pompe secondaire en déchet TFA.<br />
Une étude a été menée avec lANDRA sur la faisabilité et les travaux de préparation à réaliser afin dévacuer en pièce unitaire<br />
cette pompe vers le centre CSTFA.<br />
Après son basculement en position horizontale, le corps de pompe (partie cylindrique) a été préparé* afin dassurer son remplissage<br />
en mortier au CSTFA.<br />
A-14) TRITIUM ANALYSIS : AN ACTUAL PROBLEM FOR LARGE<br />
BUILDING DECOMMISSIONING (w/oP-59406)<br />
Pascal Fichet, Florence Goutelard, Sylvie Guegan, Aurelie Robert-Ortis,<br />
Nadine Evenat-Robic, Commissariat à l’Energie Atomique (France)<br />
Radioactive waste management is nowadays, after nearly 50 years of concern, a technical and economical challenge faced by<br />
existing nuclear power countries. In decommissioning of nuclear facilities and after disposal of the nuclear equipments (laboratory<br />
materials, glove boxes, &), the radioactive inventory of the various building materials is needed to state the working condition<br />
for dismantling.<br />
A 150 m² laboratory which accommodated preparations of 3H and 14C labeled molecules is currently under investigation in<br />
order to be dismantled in the next decade. 3H is particularly difficult to measure because of its lability and because of the low energy<br />
of its beta emission. In order to classify the various building materials, different techniques of measurements have been implemented<br />
after a grid has been marked on the floor. Firstly, a smear of each square was carried out and 3H was analyzed leading to<br />
a first radiological area classification. Secondly, the technique called digital photo stimulated luminescence (PSL) autoradiography<br />
(usually used in biology) has been developed in order to identify radioactive spots in the laboratory. This technique consists in<br />
depositing the radiation sensitive film on the floor. After an exposure time of two days, a scan by laser leads to a 2D image…<br />
A-15) REUSE OF CONDITIONALLY RELEASED STEELS; PROPOSAL AND EVALUATION<br />
OF PROCESSES FOR MANUFACTURING OF STEEL ELEMENTS AND<br />
FOR CONSTRUCTION OF SELECTED SCENARIOS (wP-59130)<br />
Peter Bezák, Eva Hajková, Frantisek Ondra, Vladimír Daniska, DECOM, a.s.;<br />
Vladimir Necas, Slovak University of Technology (Slovakia)<br />
Conditional release of steels from decommissioning projects enables controlled reuse of considerable volumes of steels. For<br />
proposal of scenarios for steel reuse, it is needed to identify and evaluate partial elementary activities of the whole process from<br />
conditioned release of steels, manufacturing of various elements up to realisation of scenarios. As the scenarios for reuse of conditional<br />
released steel are considered the technical constructions such as bridges, tunnels, roads, railway constructions and others<br />
104
Abstracts Session 39<br />
which guarantee the long-term properties over the periods of 50-100 years. The paper presents the review of activities for manufacturing<br />
of various steel construction elements made of conditionally released steels and activities for realisation of selected scenarios<br />
for reuse of such construction elements. As the starting material for manufacturing of steel elements are the ingots as the<br />
product of melting within the frame of decommissioning radioactive materials management. These ingots are re-melted in industrial<br />
facilities in order to achieve the required physical and chemical properties. Most used technique for manufacturing the steel<br />
construction elements is rolling. As the products considered in scenarios for reuse of conditionally released steels are bars for reinforcement<br />
concrete, rolled steel sheets and other general rolled steel profiles. Lists of elementary activities are…<br />
A-16) THE ASSESSMENT OF THE WASTE MANAGEMENT PLAN TO DECOMMISSIONING<br />
OF CERNAVODA NPP FOR ENVIRONMENTAL IMPACT REDUCTION (wP-59358)<br />
Gheorghe Barariu, National Authority for Nuclear Activity -<br />
Subsidiary of Technology and Engineering for Nuclear Project (Romania)<br />
At present, most of radioactive wastes generated in Romania are due to nuclear activities related to power generation at Cernavoda<br />
NPP Unit 1, commissioned in 1996. By the commissioning in 2007 of Cernavoda NPP Unit 2, nuclear power production<br />
doubled, and as a result the radioactive waste volumes doubled for this industrial activity field.<br />
Nuclear and Radioactive Waste Agency - AN&DR strategy on low and intermediate level waste disposal, has as objective the<br />
commissioning of <strong>Final</strong> Repository for Low and Intermediate Level Waste - DFDSMA until 2017. This facility is in the responsibility<br />
of AN&DR. On the other hand wastes arising from Cernavoda NPP must be treated in order to achieve the acceptance criteria<br />
of DFDSMA. Corresponding Radioactive Waste Treatment Facility - RWTF is in the responsibility of Cernavoda NPP.<br />
Main objective of the National Policy for radioactive waste management is to assure a theoretic nul negative impact or a practical<br />
minimum reasonable impact of the waste management activities on population and environment.<br />
The volume of low and intermediate level wastes that result from decommissioning of four units CANDU 6 and the environment<br />
impact reduction will be presented in this paper.<br />
The treatment facility for radioactive wastes generated by decommissioning<br />
A-17) APPLICATION OF THE DATA QUALITY OBJECTIVE PROCESS TO THE PARTIAL<br />
DE-LICENSING AT OLDBURY NUCLEAR POWER STATION (WP -59376)<br />
Denis Buckley, Magnox Ltd, Berkeley (UK)<br />
Early in 2011 Oldbury Nuclear Power station in South West England applied to the Office of Nuclear Regulation (ONR) to delicense<br />
an area of over 30 hectares of licensed land. This is the largest area of licensed land in the UK to undergo this procedure.<br />
As part of the process the site prepared a safety case to support the submission to the ONR. Also there has been a requirement to<br />
do sampling and analysis to characterise the land and show that any radioactive contamination is below the criterion for de-licensing.<br />
This has been achieved through the successful application of the Data Quality Objective (DQO) process which enabled both<br />
site and regulators to agree on the quantity of samples and the degree of analysis. The ONR has now issued the variation to Oldbury<br />
in July 2011 de-licensing approximately 32 hectares of land from regulatory control.<br />
This Paper outlines the process including the decisions and criteria that have been applied to the Sampling and Analysis at Oldbury<br />
and the Treatment and Interpretation of the data.<br />
This Paper outlines the process including the decisions and criteria that have been applied to the Sampling and Analysis at Oldbury<br />
and the Treatment and Interpretation of the data.<br />
A-18) MULTI-SITE RISK-BASED PROJECT PLANNING, OPTIMIZATION, SEQUENCING & BUDGETING<br />
PROCESS AND TOOL FOR THE INTEGRATED FACILITY DISPOSITION PROJECT (wP -59394)<br />
Jerel Nelson, Carlos Castillo, Julie Huntsman, Heather Lucek, WorleyParsons; Tim Marks, Omega Consultants (USA)<br />
Faced with the DOE Complex Transformation, NNSA was tasked with developing an integrated plan for the decommissioning<br />
of over 400 facilities and 300 environmental remediation units, as well as the many reconfiguration and modernization projects<br />
at the Oak Ridge National Laboratory (ORNL) and Y-12 Complex. Manual scheduling of remediation activities is time-consuming,<br />
labor intensive, and inherently introduces bias and unaccounted for aspects of the scheduler or organization in the process.<br />
Clearly a tool was needed to develop an objective, unbiased baseline optimized project sequence and schedule with a sound technical<br />
foundation for the Integrated Facility Disposition Project (IFDP).<br />
In generating an integrated disposition schedule, each project (including facilities, environmental sites, and remedial action<br />
units) was identified, characterized, then ranked relative to other projects. Risk matrices allowed for core project data to be extrapolated<br />
into probable contamination levels, relative risks to the public, and other technical and risk parameters to be used in the<br />
development of an overall ranking. These matrices ultimately generated a complete data set that were used in the Ranking and<br />
Sequencing Model (RSM), commonly referred to as the SUPERmodel ,for its numerous abilities to support D&D planning, prioritization,<br />
and sequencing. The SUPERmodel provides rough order-of-magnitude cost estimating,…<br />
SESSION 39B — POSTER SESSION: ENVIRONMENTAL REMEDIATION POSTERS (4.1)<br />
B-1) RADIUM REMEDIATION IN CANADA - HISTORY AND PRESENT DAY (w/oP-59157)<br />
Mark Gardiner, Michael Owen, Robert Zelmer, AECL (Canada)<br />
The environmental impact of radium remains even today. Radio-luminescent paints, radium therapy needles, mining and processing<br />
and their associated legacies have long been pursued in France, Canada, the USA and other countries. The management of<br />
these tasks provides a rich and fascinating history as well as successes and lessons learned in environmental remediation. In Canada,<br />
the radium story begins with the discovery of pitchblende on the shores of Great Bear Lake in Canadas far north and its transport<br />
south and refinement in Port Hope, Ontario. In the earliest days, the leading characters were the LaBine brothers, involved in<br />
exploration and mining, and at the recovery and refining end, Carl French and Marcel Pochon, a protégé of Marie Curie, all associated<br />
with the Eldorado Mining and Refining Company .<br />
105
Session 39 Abstracts<br />
To the current day in Canada, the work of environmental remediation of the radium legacy largely follows the trail of these<br />
individuals, just as in France, a parallel effort follows the trail of Madame Curie. The Low-Level Radioactive Waste Management<br />
Office is the agent of the Canadian government for its responsibilities regarding the work at the affected sites and the management<br />
of the related wastes. The Office operates programs and facilities to…<br />
B-2) MATHEMATICAL MODELING OF REACTIVE TRANSPORT IN GROUNDWATER WITH METALS<br />
AND DISSOLVED ISOTOPES 226RA AND 228RA, USIN, SÃO PAULO, BRAZIL (w/oP-59245)<br />
Rodrigo Raposo de Almeida, Federal Fluminense University; Valter Mortágua, Industrias Nucleares do Brasil;<br />
Felipe Rosa, Luciano Magalhaes, Universidade Federal Fluminense (Brazil)<br />
This paper aims to present the results of the analytical model of transport and the mathematical model of flow and transport of<br />
radionuclides, considering the decay and adsorption of the byproducts. The study area is located in Sao Paulo, the largest city in<br />
Brazil and Latin America with about 11 million inhabitants, and it is a former unit of processing of rare earths which ran between<br />
the years 1960 and 1996 named the Plant Interlagos (USIN). The work focus is on groundwater contamination that occurred inside<br />
Warehouse A. This contamination of soil and groundwater occurred about in 1991 due to a crack and leak from a box of separation<br />
of ammonium chloride containing some dissolved radionuclides. The main source of contamination is no longer active, however<br />
the residual phase in the vadose zone still there as a secondary source of contamination. Monitoring of groundwater is done periodically<br />
since 1992, but only in 2007 a detailed groundwater study was undertaken from the impacted area. This study aimed to<br />
detail the plume of contamination of metals and radionuclide in Warehouse A (Galpão A). With the software 3GEO Bioscreen SI<br />
was developed an analytical model of transportation to establish and calibrate the parameters…<br />
B-3) QUANTIFYING THE RETENTION OF FOAM FORMULATION COMPONENTS TO SEDIMENTARY<br />
PHASES TO ENABLE PREDICTIONS OF MOBILITY AND TREATMENT EFFICACY (w/oP-59369)<br />
Rosa Ramirez, DOE EM; Danielle Jansik, Dawn Wellman, Pacific Northwest National Laboratory (USA)<br />
Deep vadose zone remediation remains the most challenging remediation problem in the DOE Complex. Foam delivery technology<br />
is being developed as a method for delivering remedial amendments within vadose zone environments for in situ contaminant<br />
stabilization. Thus far, the physical propagation of foam within subsurface media has been evaluated and quantified. However,<br />
foam propagation is a product of surfactant sorption which directly impacts foam stability. In order to predict the stability of<br />
foam during subsurface transport it is necessary to quantify the sorption of foam components as a function of concentration, competitive<br />
sorption, sediment mineralogy, and temperature. This investigation provides the results of standard static batch test quantifying<br />
these relationships. High Performance Liquid Chromatography (HPLC) was used to measure surfactant concentrations. The<br />
results of this investigation provide necessary understanding to predict foam stability during subsurface transport and determination<br />
of the remedial radius of influence. This study is part of a multiple step process for demonstrating the feasibility of foam transport<br />
to distribute amendments within in the vadose zone.<br />
B-4) TECHNIQUES OF RADIOACTIVE SOIL PROCESSING AT REHABILITATION<br />
OF CONTAMINATION TERRITORIES. (wP-59199)<br />
Victor Volkov, Alexander Chesnokov, Alexey Danilovich, Yury Zverkov, Sergey Koltyshev,<br />
Sergey Semenov, Anatoly Shisha, RRC Kurchatov Institute (Russia)<br />
Rehabilitation of nuclear- and radiation objects assumes dealing with and removal of considerable volumes of a radioactive<br />
soil. A similar situation was faced at the remediation of such sufficiently large objects, as old radioactive waste storages at the territory<br />
of «Kurchatov Institute» and elimination of consequences of radiation accident at Podolsk plant of nonferrous metals. At<br />
rough estimates the volumes of a radioactive soil at territory of «Kurchatov institute» were 15-20 thousand cub.m, volumes of a<br />
removed soil at carrying out of urgent measures in territory of Kirovo-Chepetsk chemical plant exceeded 20-25 thousand cub.m,<br />
volumes of a low active waste at the territory of Podolsk plant may reach 20 thousand cub.m.<br />
Such considerable volumes demand creation of technologies of their processing, an effective measuring technique of levels of<br />
their contamination and ways of considerable (in times) decrease of their volumes at the expense of decontamination or separation.<br />
Works have been aimed at the decision of these problems at carrying out of rehabilitation of territory «Kurchatov institute». During<br />
works technologies of radiation and water-gravitational separation of a radioactive soil have been offered and are realized in<br />
practice. A facility of water -gravitational separation of the soil was created and used within…<br />
B-5) OPTIMISATION (SAMPLING STRATEGIES AND ANALYTICAL PROCEDURES)<br />
FOR SITE SPECIFIC ENVIRONMENT MONITORING AT THE AREAS OF<br />
URANIUM LEGACY SITES CONTAMINATION CONCERN IN UKRAINE (wP-59045)<br />
Oleg Voitsekhovych, Tatiyana Lavrova, Alexander Kostezh, Ukrainian Hydrometeorological Institute (Ukraine)<br />
There are many sites in the world, where Environment are still under influence of the contamination related to the Uranium<br />
production carried out in past. Author’s experience shows that lack of site characterization data, incomplete or unreliable environment<br />
monitoring studies can significantly limit quality of Safety Assessment procedures and Priority actions analyses needed for<br />
Remediation Planning. During recent decades the analytical laboratories of the many enterprises, currently being responsible for<br />
establishing the site specific environment monitoring program have been significantly improved their technical sampling and analytical<br />
capacities. However, lack of experience in the optimal site specific sampling strategy planning and also not enough experience<br />
in application of the required analytical techniques, such as modern alpha-beta radiometers, gamma and alpha spectrometry<br />
and liquid-scintillation analytical methods application for determination of U-Th series radionuclides in the environment, doesnt<br />
allow to these laboratories to develop and conduct efficiently the monitoring programs as a basis for further Safety Assessment in<br />
decision making procedures. This paper gives some conclusions, which were gained from the experience establishing monitoring<br />
programs in Ukraine and also propose some practical steps on optimization in sampling strategy planning and analytical procedures<br />
to be applied for the area required Safety assessment and justification for its potential remediation and safe management.<br />
106
Abstracts Session 39<br />
SESSION 39C — POSTER SESSION: MAJOR INSTITUTIONAL ISSUES IN<br />
ENVIRONMENTAL MANAGEMENT / PUBLIC INVOLVEMENT (5.1)<br />
C-1) VIRTUAL REALITY TECHNOLOGY FOR RADIATION VISUALISATION DURING<br />
THE REMEDIATION AT ANDREEVA BAY IN RUSSIA AS SUPPORT TO<br />
OPERATIONAL AND REGULATORY SUPERVISION (wP-59400)<br />
Niels-Kristian Mark, Institute for Energy Technology,<br />
Malgorzata Sneve, Norwegian Radiation Protection Authority (Norway)<br />
The Norwegian Radiation Protection Authorities (NRPA) has since 1996 carried out a program of regulatory support projects,<br />
funded by the Norwegian Ministry of Foreign Affairs (NMFA) The objective of the program has been to support the Russian civilian<br />
and military regulators, the Federal Medical Biological Authorities of Russia (FMBA) and the Federal Environmental, Industrial<br />
and Nuclear Supervision Service of Russia, as well as the corresponding nuclear and radiation safety authority within the Russian<br />
Ministry of Defense with development and implementation of methods and tools for better regulatory supervision of the Andreeva<br />
Bay and Gremikha Sites of Temporary Storage (STS) for Spent Nuclear Fuel (SNF) and Radioactive Waste (RW).<br />
In 2005-2009 regulatory investigations were completed at the Andreeva Bay and Gremikha within the collaborative NRPA-<br />
FMBA program. The radiation and radio-ecological situation was assessed, and criteria and regulations of the STS remediation<br />
were developed, as well as the guidance for their application for three possible options of environmental remediation (conservation,<br />
conversion and liquidation). As part of the project the Federal Medical-Biological Centre, a technical support organisation to<br />
FMBA, developed the DOSEMAP and DATAMAP applications for the FMBA, supporting radiation risk monitoring, worker radiation<br />
exposure control and deeper understanding of the evolution of…<br />
C-2) TAKING RISK ASESSMENT AND MANAGEMENT TO THE NEXT LEVEL (wP-59395)<br />
Jerel Nelson, Russel Lee Morton, WorleyParsons Polestar; Carlos Castillo, WorleyParsons;<br />
James T. McSwain, Terragraphics; George Dyer, Natalie Johnson, WorleyParsons;<br />
Gary Nick Kruskall, Link Technologies (USA)<br />
A multi-level (facility and programmatic) risk assessment was conducted for the facilities in the Nevada National Security Site<br />
(NNSS) Readiness in Technical Base and Facilities (RTBF) <strong>Program</strong> and results were included in a new Risk Management Plan<br />
(RMP), which was incorporated into the fiscal year (FY) 2010 Integrated Plans. Risks, risk events, probability, consequence(s),<br />
and mitigation strategies were identified and captured, for most scope areas (i.e., risk categories) during the facilitated risk workshops.<br />
Risk mitigations (i.e., efforts in addition to existing controls) were identified during the facilitated risk workshops when the<br />
risk event was identified. Risk mitigation strategies fell into two broad categories: threats or opportunities. Improvement projects<br />
were identified and linked to specific risks they mitigate, making the connection of risk reduction through investments for the annual<br />
Site Execution Plan.<br />
Due to the amount of that was collected, analysis to be performed, and reports to be generated, a Risk Assessment/ Management<br />
Tool (RAMtool) database was developed to analyze the risks in real-time, at multiple levels, which reinforced the site-level<br />
risk management process and procedures. The RAMtool database was developed and designed to assist in the capturing and analysis<br />
of the key elements of risk: probability, consequence, and impact. The…<br />
C-3) RADIOACTIVE WASTE, FROM MYTH TO REALITY: THE STAKES FOR<br />
ANDRA’S EDUCATIONAL COMMUNICATION EFFORTS (w/oP-59287)<br />
Annabelle Comte, Andra (France)<br />
Andra is responsible for proposing and implementing industrial management solutions for France’s radioactive waste. Andra’s<br />
goal is to ensure that everyone has the opportunity to make up his or her own mind on a subject that generates such heated debate<br />
within our society. This duty of communication is enshrined in law and is an integral part of Andra’s activities, in the same way as<br />
research, industry and risk management.<br />
Because the subject of radioactive waste is a complex one and concerns such a variety of audiences, Andra adapts its communication<br />
policy so that it is accessible to all, according to individual needs and levels of interest.<br />
For the “non-specialists” (general public, young people, etc.) Andra proposes a system built around education and awarenessraising.<br />
Its aim is to make the subject of radioactive waste accessible to and comprehensible to as many as possible.<br />
Its educational communication approach is built on 3 pillars: first and foremost information, the keystone of any system of<br />
communication, then explanation and finally sharing with the legitimate stakeholders in this pedagogical approach.<br />
Providing dependable information Andra offers information that is appropriate to the level of knowledge of its audiences and<br />
uses all communication media, from the most…<br />
SESSION 40— D&D MANAGEMENT APPROACHES AND PLANNING TOOLS (3.6)<br />
1) IMPLEMENTATION OF THE STANDARDISED LISTING INTO DECOMMISSIONING<br />
COSTING; EXAMPLES AND RELATED IAEA PROJECTS (wP-59313)<br />
Vladimír Daniska, DECOM, a.s.; Michele Laraia, Paul Dinner, Patrick O’Sullivan, IAEA (Slovikia/Austria)<br />
In 1999, IAEA, the OECD Nuclear Energy Agency and the European Commission jointly proposed a standardised listing of<br />
activities to serve as a common basis for decommissioning cost estimates and thus promote greater harmonisation. This standardised<br />
structure, which is based on activities at three hierarchical levels, is currently being updated based on the experience gained<br />
over ten years of use. This paper comprises two main parts: in the first part, the revised standardised list of activities is presented,<br />
together with guidance on its use in decommissioning costing. The three-level hierarchical structure has been retained though with<br />
several detailed changes to ensure comprehensiveness and avoid ambiguity.<br />
107
Session 40 Abstracts<br />
The second part the paper provides examples of cost methodologies based on the standardised list, including a cost estimation<br />
model for research reactors and a spreadsheet-based cost estimation model, which might be used for scoping purposes or as a training<br />
tool for cost estimators. The cost estimation model for research reactors at IAEA is intended for preliminary cost estimations<br />
in IAEA member countries with limited previous experience in decommissioning costing. In this case, costs are determined largely<br />
at the second level of the hierarchical structure of activities, as the more detailed cost information required for…<br />
2) USE OF SOURCE TERM AND AIR DISPERSION MODELING IN PLANNING DEMOLITION<br />
OF HIGHLY ALPHA-CONTAMINATED BUILDINGS (wP-59254)<br />
James G Droppo, Bruce A. Napier, Jeremy P. Rishel, Pacific Northwest National Laboratory;<br />
Richard W. Bloom, CH2M Hill Plateau Remediation Company (USA)<br />
The current cleanup of structures related to cold-war production of nuclear materials includes the need to demolish a number<br />
of highly alpha-contaminated structures. The process of planning for the demolition of such structures includes unique challenges<br />
related to ensuring the protection of both workers and the public. Pre-demolition modeling analyses were conducted to evaluate<br />
potential exposures resulting from the proposed demolition of a number of these structures. Estimated emission rates of transuranic<br />
materials during demolition are used as input to an air-dispersion model. The climatological frequencies of occurrence of peak<br />
air and surface exposures at locations of interest are estimated based on years of hourly meteorological records. The modeling<br />
results indicate that downwind deposition is the main operational limitation for demolition of a highly alpha-contaminated building.<br />
The pre-demolition modeling directed the need for better contamination characterization and/or different demolition methodsand<br />
in the end, provided a basis for proceeding with the planned demolition activities. Post-demolition modeling was also conducted<br />
for several contaminated structures, based on the actual demolition schedule and conditions. Comparisons of modeled and<br />
monitoring results are shown. Recent monitoring data from the demolition of a UO3 plant shows increments in concentrations that<br />
were previously identified in the pre-demolition modeling…<br />
3) HOW AND INTEGRATED CHANGE PROGRAMME HAS ACCELERATED THE REDUCTION<br />
IN HIGH RISK AND HIGH HAZARD NUCLEAR FACILITIES AT SELLAFIELD (wP-59014)<br />
Angela Mackintosh, Sellafield Ltd. (UK)<br />
For over five decades the Sellafield Site has been central to the UKs nuclear programme. Sellafield Ltd is managed by NMP<br />
(Nuclear Management Partners), a consortium of URS, AMEC and AREVA and is focussed on the decommissioning of historical<br />
facilities.<br />
When the activity of Decommissioning commenced in the late 1980s the site focus at that time was on commercial reprocessing<br />
and waste management. Now through the implementation of an integrated company change programme, emphasis has shifted<br />
towards accelerated risk and hazard reduction of degraded legacy plants with nuclear inventory whilst ensuring value for money<br />
for the customer, the Nuclear Decommissioning Authority (NDA).<br />
This paper will describe the management approach that is being taken and the planning tools that are being applied by the Site<br />
owners in delivering an integrated change programme across the Decommissioning Directorate.<br />
The paper will explain how the management approach to change uses Peer Assist, Rapid Improvement <strong>Events</strong>, Organisational<br />
Review Self Evaluation, Value Stream Analysis and Accelerated Improvement <strong>Events</strong> as improvement tools. Use of these has<br />
enabled downsizing of the organisation, driven out hundreds of man day efficiencies within the maintenance and asset management<br />
areas, improved the management of spares reducing annual costs by £1000s, improved Commercial…<br />
4) USE OF IN-SITU GAMMA SPECTROSCOPY DURING NUCLEAR<br />
POWER PLANT DECOMMISSIONING (w/oP-59340)<br />
Richard McGrath, Karen Kim, Electric Power Research Institute (USA) - Presentation by Sean Bushart, EPRI (USA)<br />
The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The<br />
Nuclear Power Plant Decommissioning Technology <strong>Program</strong> conducts research and develops technology for the safe and efficient<br />
decommissioning of nuclear power plants.<br />
One of the key objectives of the EPRI Decommissioning Technology <strong>Program</strong> is to capture the good practices and lessons<br />
learned from plants currently undergoing decommissioning. Several major plant decommissioning programs have been successfully<br />
completed, so EPRI is documenting relevant experiences to aid future decommissioning activities, both in the United States and<br />
internationally. In-situ Gamma Spectroscopy is powerful technology with the potential for widespread application in nuclear power<br />
plant radiological surveys.<br />
Due to leakage and other events that may occur during nuclear power plant operations, soil, concrete and bedrock have the<br />
potential to become contaminated, and therefore must be characterized to demonstrate that they meet strict regulatory site release<br />
limits. The radiological surveys conducted during power plant decommissioning have historically been very labor intensive, time<br />
consuming and often extend decommissioning duration. The use of hand-held survey meters was typical during early decommissionings.<br />
As engineers gained experience, they often replaced the hand-held meters with advanced technologies such as the In-situ<br />
Gamma Spectroscopy instruments. The…<br />
5) LEGACY RADIOACTIVE WASTE STORAGE - MAGNOX SWARF STORAGE<br />
SILO LIQUOR EFFLUENT MANAGEMENT (wP-59271)<br />
Stephen Le Clere, Sellafield Ltd (UK)<br />
The liquid effluent activity arising from Sellafield Ltds Magnox Swarf Storage Silo (MSSS) emptying operations represents<br />
the greatest liquid effluent treatment challenge within the companys Legacy Ponds and Silos portfolio.<br />
The Magnox Swarf Storage Silo (MSSS) was constructed to provide an underwater storage facility for irradiated magnox<br />
cladding swarf that was removed from fuel prior to processing.<br />
Construction of the original silo was initiated in the early 1960s, as the existing Pile Fuel Cladding Silo reached its storage<br />
capacity however the original silo was filled by 1972 so three further silo extensions were constructed between the early 1970s and<br />
mid-1980s.<br />
108
Abstracts Session 40<br />
A significant programme of work has been underway over the last two decades, to support the programmes strategic intent of<br />
retrieving and treat all legacy wastes and remediate the structures of both the legacy plant and the new build construction plants<br />
necessary to support decommissioning.<br />
The paper will look at the challenges faced by the team as they ready the facility for retrievals and decommissioning and discuss<br />
how these were managed or overcome through a coordinated programme of work.<br />
This will include a review of the significant asset restoration programme which culminated recently in the commencement of<br />
production liquor transfers…<br />
6) EXPERIENCE OF APPLICATION OF NEW REMOTE CONTROLLED INSTRUMENTS FOR SCANNING OF<br />
DISTRIBUTION OF RADIOACTIVE CONTAMINATION IN ROOMS WITH HIGH DOSE RATE (wP-59354)<br />
Vyacheslav Stepanov, Alexey Danilovich, Oleg Ivanov, Victor Potapov, Sergey Smirnov,<br />
Anatoly Volkovich, NRC Kurchatov Institute (Russia)<br />
When carrying out the decommissioning of nuclear facilities is necessary to measure the distribution of radioactive contamination<br />
in the rooms and the equipment at high levels of background radiation. In the decommissioning of the reactor in the MR<br />
Research Center “Kurchatov Institute” for such problems is developed and applied a few special systems with remote control. For<br />
a survey of high-level objects used mounted on the robot radiometric system [V.E. Stepanov, etc. Using collimated radiometer systems<br />
mounted on the robot for inspection of storage Brokk CPS inside the reactor MR Research Center “Kurchatov Institute”//<br />
Atomic Energy. 2010. v.109. no4. P. 194]. To determine the composition of pollutants and use a portable collimated spectrometric<br />
system [V.E. Stepanov et. Al. Remotely controlled collimated detector to measure the distribution of radioactive contamination //<br />
Atomic Energy. 2010. v.109. no2. S. 106]. To obtain a detailed distribution of contamination of used remote-controlled gamma camera<br />
[Stepanov V. E., et al. Application of portable gamma camera for the control on extraction of the radioactive wastes from temporal<br />
storage in territory of RRC Kurchatov Institute// ICEM05/DECOM05 Glasgow 2005, Abstract Book pp.97]. Described works<br />
conducted under the Federal <strong>Program</strong> for Nuclear and Radiation Safety of Russia.<br />
7) HUMAN AND ORGANISATIONAL FACTORS AS KEY LEVERS OF PERFORMANCE<br />
IN D&D PROJECT MANAGEMENT (W/OP-59323)<br />
Thierry Flament, Bertrand Willmann, Grégoire de Laval, Jean-Louis Lemarch, Alain Cordoba, AREVA (France)<br />
In a number pf D&D projects, the type of installations to be dismantled and the variety of their equipments (glove-boxes,<br />
tanks&) and the products present on site (plutonium, uranium) in the form of powder are making many operations manual ones.<br />
Key phases in HR and organisation management:<br />
• The first D&D experience, the learning curve ramp-up<br />
• To begin any project, you usually try to benefit from benchmark of similar projects to be able to build up the first scenario,<br />
by using the best practices. The first experimental team consisted of operators who already had experienced dismantling<br />
at least once in the course of their career.This first dismantling operation is preferably to be conducted on an installation<br />
relatively poorly contaminated. This was to implement the correct techniques thus reducing the consequences of a possible<br />
unforeseen event.<br />
The capitalisation on the return on experience<br />
The success of this first dismantling site operation allowed us to implement a process of experience feedback to build the scenarios<br />
and the operating procedures of the following sites. In particular, targeted safety-security stop points are positioned for validation<br />
on the operations by people responsible for safety and security.<br />
• HR training<br />
• Implementation of new equipments (saws, stalls&) allows experimental…<br />
8) DEVELOPMENT OF COMPUTER PROGRAM FOR ESTIMATING DECOMMISSIONING COST (wP-59037)<br />
HakSoo Kim, JongKil Park, Nuclear Engineering & Technology Institute (Korea)<br />
The programs for estimating the decommissioning cost have been developed for many different purposes and applications. The<br />
estimation of decommissioning cost is required a large amount of data such as unit cost factors, plant area and its inventory, waste<br />
treatment, etc. These make it difficult to use manual calculation or typical spreadsheet software such as Microsoft Excel. The cost<br />
estimation for eventual decommissioning of nuclear power plants is a prerequisite for safe, timely and cost-effective decommissioning.<br />
To estimate the decommissioning cost more accurately and systematically, KHNP, Korea Hydro and Nuclear Power Co.<br />
Ltd, developed a decommissioning cost estimating computer program called “DeCAT-Pro”, which is Decommissioning Cost<br />
Assessment Tool Professional. (Hereinafter called “DeCAT”) This program allows users to easily assess the decommissioning cost<br />
with various decommissioning options. Also, this program provides detailed reporting for decommissioning funding requirements<br />
as well as providing detail project schedules, cash-flow, staffing plan and levels, and waste volumes by waste classifications and<br />
types. KHNP is planning to implement functions for estimating the plant inventory using 3-D technology and for classifying the<br />
conditions of radwaste disposal and transportation automatically.<br />
SESSION 41 — D&D TECHNOLOGIES - PART 2 OF 2 (3.13)<br />
1) AN INNOVATIVE PROCESS FOR SEGMENTING OF GUIDE TUBES (wP-59029)<br />
Patrick (PJ) Gobert, Pierre-Henri Ponchon, Stefan Fallström,<br />
Joseph Boucau, Westinghouse Electric Company (Belgium/France/Sweden)<br />
The purpose of this paper is to describe an innovative process for segmenting PWR Guide Tubes (GT’s) and the service (training<br />
and execution) that can be performed successfully and safely.<br />
Over time, some utilities are replacing control rod GTs and store them in temporary disposal facilities. Due to lack of space, it<br />
is sometimes needed to cut and condition them in waste packages for final disposal and waste treatment.<br />
Based on its more than 20 years of strong experience and lessons learned in the development of nuclear components segmentation<br />
and packaging technology, Westinghouse has recently developed a complete solution for cutting and consolidating GTs.<br />
109
Session 41 Abstracts<br />
One of the challenges related to such equipment is to consider two routes for the waste management: one for the highly activated<br />
segments and another for the less activated segments.<br />
The length of the segments has been defined to minimize the volume of highly activated waste and therefore develop a process<br />
which is adapted to the size of containers specified by the customer. A model with five cutting operations and generating six segments<br />
has been chosen.<br />
In order to minimize risks and ensure safety for people and facilities, radiological studies were performed for various configurations.<br />
All…<br />
2) ASSAY OF PLUTONIUM CONTAMINATED WASTE BY GAMMA SPECTROMETRY (wP-59039)<br />
Ian Adsley, Michael Green, Ian Pearman, Mike Davies, Nuvia Limited (UK)<br />
The extreme toxicity of plutonium necessitates the segregation of plutonium contaminated materials (PCM) with extremely<br />
small (sub-?g) levels of contamination. The driver to accurately measure these small quantities of plutonium within (relatively)<br />
large volumes of waste is (in part) financial. The range of waste costs in the UK varies considerably typically by an order of magnitude<br />
for each step in category from Exempt, through VLLW, LLW and ILW.<br />
Within the UK, there has been a historical reluctance to use low energy gamma radiation to sentence PCM because of the potential<br />
for self attenuation by dense materials. This is unfortunate because the low-energy gamma radiation from PCM offers the only<br />
practicable technique for segregating PCM within the various LLW and sub-LLW categories. Whilst passive neutron counting techniques<br />
have proved successful for assay of waste well into the ILW category, a cursory study of the neutron yield data from spontaneous<br />
fission and ?-n reactions reveals that these techniques are barely capable of detecting mg quantities of plutonium let alone<br />
the sub-?g quantities present in LLW.<br />
This paper considers the use of two types of gamma detector for assay of PCM: the thin sodium iodide FIDLER (Field Instrument<br />
for the Detection…<br />
3) REUSE OF CONDITIONAL RELEASED MATERIALS FROM DECOMMISSIONING; A REVIEW OF<br />
APPROACHES AND SCENARIOS WITH LONG-TERM CONSTRUCTIONS (w/oP-59149)<br />
Vladimír Daniska, Jozef Pritrsky, Frantisek Ondra, Ivan Rehák, Matej Zachar, DECOM, a.s,;<br />
Vladimir Necas, Slovak University of Technology (Slovakia)<br />
Paper presents the overall scope and actual results of the project for evaluation of representative scenarios for reuse of conditionally<br />
released materials from decommissioning. Aim of the project is to evaluate the possibilities of reuse of conditionally<br />
released steels and concrete in technical constructions which guarantee the long-term preservation of design properties over periods<br />
of 50-100 years. Interaction of conditionally released materials with public is limited and predictable due to design and purpose<br />
of selected constructions and due to fact that in many scenarios these materials are embedded in non-radioactive materials<br />
such as bars in reinforced concrete. Workers scenarios for preparation, operation and maintenance of these constructions are<br />
analysed in detail including the manufacturing of elements for these constructions. Project aims to evaluate the scenarios of reuse<br />
of conditionally released materials in a complex way in order to develop the data for designers of scenarios and to evaluate the volumes<br />
of conditionally released materials based on facility (to be decommissioned) inventory data. The long-term constructions considered<br />
are bridges, tunnels, roads, railway constructions, industrial buildings, power industry equipment and others. Evaluation<br />
covers following areas:<br />
• Analysis of activities for manufacturing of reinforcement bars, rolled steel sheets and other steel elements and…<br />
4) REMEDIATION OF A VENTILATION DUCT CONTAMINATED BY PA-231 (wP-59248)<br />
Pete Burgess, Nuvia Ltd; Clare Irving, Forest Environmental; Keith Stevens, Nuvia Ltd, (UK)<br />
Cambridge University had worked in the 1960s and 1970s with Pa-231, a decay product of U-235. The fume cupboards discharged<br />
into ventilation ducting made from asbestos cement. The university wished to refurbish the laboratory and the RPA had<br />
negotiated over many years with the Environment Agency to set up a project to remove the ducting both to reduce the radiological<br />
hazards and as part of a programme to ,remove unwanted circuits and upgrade the ventilation system to modern standards. Contamination<br />
levels were significant and low dose rates were measurable on the external surface. The aim was to be able to remove<br />
the ducting and treat it as asbestos waste, rather than to have to treat the debris as asbestos contaminated radioactive waste. The age<br />
of the contaminant was such that a large fraction of the decay chain had grown in, giving a mixture of alpha, beta and gamma emissions.<br />
The most useful nuclides for surface monitoring were Pb-211 and Tl-207, both of which are energetic beta emitters. A wide<br />
energy range beta detector was used, but it was fitted with a filter to absorb any alpha radiation which otherwise would have contributed<br />
to the signal for good surfaces but not…<br />
5) MEASUREMENT OF PLUTONIUM CONTAMINATION THROUGH PAINT USING A FIDLER PROBE (wP-59250)<br />
Robert Clark, Pete Burgess, Nuvia Ltd; Ian Croudace, GAU-Radioanalytical Laboratories (UK)<br />
Alpha contamination detection usually relies on good surface conditions - smooth, clean and flat. However, in many circumstances,<br />
this is not the case, or it may be that there is a significant chance that contamination has been deliberately or accidentally<br />
painted over. The alpha emitting isotopes of plutonium also emit significant L x-rays in the 11 to 20 keV energy range, as does Am-<br />
241, which also emits a 60 keV gamma with a 36 % probability. These X-rays are unattenuated to any extent in air over a range<br />
of 1 metre. They also penetrate paint significantly. The Fidler probe was designed as an efficient detector of these X and gamma<br />
radiations. The window is thin beryllium and the scintillator is thin sodium iodide. This leads to a very efficient detection of both<br />
the X-rays in question and the 60 keV gamma radiation while keeping the background as low as possible. The signal from such a<br />
detector can be processed in several ways gross counting above a threshold, counting in regions of interest or full spectrometry.<br />
The advantages of the latter include the minimisation of background, easy background correction, the ability to look at the recorded<br />
X-ray spectrum and the…<br />
110
Abstracts Session 41<br />
6) THE USE OF STANDARD ALPHA AND BETA SURFACE SCINTILLATION CONTAMINATION MONITORS TO<br />
CONFIRM THE CONTAMINATION FINGERPRINT AND TO CHECK ON SOURCE QUALITY (wP-59249)<br />
Pete Burgess, Nuvia Ltd (UK)<br />
Normally, alpha and beta surface contamination monitors are used with a simple counting threshold, i.e. any pulse over a predetermined<br />
amplitude is counted. This is very different from gamma monitoring, where the use of counting windows is very popular<br />
and the use of full multi-channel analysis is common. Many current surface contamination ratemeters have the capacity to<br />
drive dual phosphor detectors and can be set up to provide alpha and beta channels. Effectively, the beta channel is a counting window,<br />
i.e. all pulses which are bigger than the threshold and smaller than the alpha threshold are counted. Larger pulses go into the<br />
alpha channel.<br />
This paper addresses how this can be used with beta only and alpha only detectors to provide information on the source. The<br />
detector is set up conventionally to a plateau for the lowest beta energy anticipated. The instrument is then switched to alpha+beta<br />
mode and the alpha threshold set to 3 times the beta threshold. With this set up, the alpha to beta channel count rate ratio varies<br />
smoothly by a factor of 14 between Y-90 (Emax 2.27 MeV) and C-14 (Emax 0.16 MeV). Hence the instrument can be used to estimate<br />
the energy of an…<br />
7) CLEARANCE OF BUILDINGS OF NPP WÜRGASSEN (GERMANY) USING<br />
AN INNOVATIVE CLEARANCE CONCEPT (wP-59280)<br />
Stefan Woerlen, Marco Steinbusch, Alexander Kummer,<br />
Stefan Thierfeldt, Frank Schartmann, Brenk Systemplanung (Germany)<br />
The nuclear power plant Würgassen in Germany entered into decommissioning in 1995. The project has currently advanced to<br />
the clearance of the buildings. Clearance of buildings has commenced in 2007 with establishing the clearance procedure in pilot<br />
rooms. It has entered the productive phase in 2010 and will last until about 2014.<br />
In 2007, Brenk Systemplanung has been commissioned by E.ON / NPP Würgassen to perform clearance of the pilot rooms in<br />
the turbine building as well as of rooms with higher contamination levels in other buildings in 2010 and 2011. It has been one of<br />
the goals of this work to establish an innovative clearance procedure which would not rely on 100% surface measurements but<br />
which should be based on the use of in situ gamma spectrometry and the application of approaches to minimise the number of clearance<br />
measurements.<br />
Central points of the concept for clearance of buildings which is presented in this paper were the establishment of averaging<br />
areas of up to 10 m², which is an ideal size for the use of in situ gamma spectrometry, and the application of statistical methods,<br />
which allow an efficient performance of the clearance measurements. As a first step the measurement…<br />
8) CHARACTERIZATION OF IRAQ’S REMOTE NUCLEAR FACILITIES<br />
FOR DECOMMISSIONING AND WASTE MANAGEMENT (wP-59167)<br />
Fouad Al-Musawi, Adnan S. Jarjies, Ministry of Science and Technlogy;<br />
Ross Miller, Sandia National Laboratories (Iraq/USA)<br />
The Government of Iraq (GOI) has engaged serious efforts to decommission and dismantle former nuclear facilities. The GOI<br />
has only preliminary information on some of the former nuclear facilities, and this paper summarizes the missions that were undertaken<br />
to characterize those facilities. The facilities are located at various sites throughout Iraq, from locations close to Baghdad to<br />
those in the north and far western desert areas. Some of the facilities, such as those at the Al Tuwaitha Nuclear Research Center<br />
have been visited and somewhat characterized. Other facilities, including the following, have not been visited or thoroughly characterized.<br />
• Akashat Mine, Uranium ore production<br />
• Al Qaim, Uranium enrichment facility<br />
• Al Jesira, Uranium feed stock production facility<br />
• Adaya, Burial location for contaminated equipment<br />
• Al Tarmiya,Electromagnetic isotope separation site<br />
• Rashdiya, Centrifuge development center<br />
• Djerf al Naddah, Spent fuel storage facility<br />
Missions were conducted to develop an inventory the buildings/structures that need to be included in decommissioning/dismantlement<br />
efforts. The number of buildings, type of construction, size and general condition of the buildings was noted. In addition,<br />
attempts were made to determine contamination levels and types on surfaces, equipment, rubble, etc. This information will<br />
be used to support…<br />
SESSION 42 — LIQUID WASTE TREATMENT PROCESS AND EXPERIENCE (1.8)<br />
1) NUCLIDE SEPARATION BY HYDROTHERMAL TREATMENT AND ION EXCHANGE (wP-59217)<br />
Georg Braehler, Ronald Rieck, NUKEM Technologies GmbH; Valentin Avramenko, Valentin Sergienko,<br />
Sergej Shmatko, Valentin Dobrzhanskyi, Institute of Chemistry FEBRAS; Elmar Antonov, NTP (Germany/Russia)<br />
Liquid low level radioactive effluents, when solidified in e g. cement matrix, contribute to a significant extend to the waste<br />
amount to be disposed of in final repositories.<br />
Accordingly, since many years scientists and engineers investigate processes to remove the radioactive nuclides selectively<br />
from the effluents, to split the raw solution into two separate fractions: a large fraction with activity concentrations below the limits<br />
for free release; and a small fraction, containing the activity in concentrated form one g ion exchanger materials (ion exchange<br />
has proven to be the most promising method for such nuclide separation).<br />
The challenge to be taken up is: When (and this is most often the case) the effluent contains organic materials and complexing<br />
agents, the formation of e. g. the 60-Co-EDTA complex prohibits its fixation to the ion exchangers.<br />
Accordingly the complexing agent needs to be removed or destroyed.<br />
111
Session 42 Abstracts<br />
The Institute for Chemistry of the Russian Academy of Sciences has applied the method of hydrothermal treatment (at elevated<br />
temperature and pressure, 200 °C, 200 bar), supported by Hydrogen peroxide oxidation, to allow virtually complete removal of<br />
radioactive nuclides on inorganic ion exchangers.<br />
Pilot plants have been operated successfully in Russian power stations, and an…<br />
2) DECONTAMINATION OF STRONTIUM FROM LIQUID RADIOACTIVE<br />
WASTES BY SODIUM NONATITANATE (wP-59083)<br />
Merceille Aurélie, CEA Marcoule; Agnès Grandjean, Institut de Chimie Séparative de Marcoule;<br />
Yves Barre, CEA Marcoule (France)<br />
Environmental impact of toxic, biological and radioactive pollutants release is of great importance for all industrial societies<br />
today. The development of efficient process for purification filtration and waste removal- of these industrials effluents is booming.[1]<br />
Nuclear industry produces a wide range of radioactive liquid effluents. Many of these wastes need treatment in order to<br />
reduce the quantities of radioactive contaminants and of course to reduce human exposure. 90Sr is one of the major pollutants in<br />
nuclear liquid wastes. A promising way for extraction of this radioelement from mobile phase (liquid) to a solid phase is the use of<br />
specific ion exchange solids. Contrary to conventional organic ion exchange resins, inorganic ion exchangers possess a number of<br />
advantages such as superior chemical, thermal and radiation stability.<br />
For strontium removal from aqueous solutions, many inorganic ion exchange solids are described in the literature. One of them<br />
is sodium nonatitanate [3] which seems to be a very good candidate for this use. We present here a study of the effect of synthesis<br />
temperature on the kinetics and on the adsorption capacity of this ion exchanger [2]. For this purpose, first, three materials were<br />
synthesized at 100°C, 160°C and 200°C. They were compared thanks…<br />
3) RUSSIA: RESULTS AND PROSPECTS OF LIQUID SOLIDIFICATION<br />
EXPERIMENTS AT ROSATOM SITES (w/oP-59112)<br />
Dennis Kelley, Pacific Nuclear Solutions (USA)<br />
Ongoing experimental work has been underway at selected nuclear sites in the Russian State Atomic Energy Corporation<br />
(ROSATOM) during the past two years to determine the effectiveness, reliability, application and acceptability of high technology<br />
polymers for liquid radioactive waste solidification. The long term project is funded by the U.S. Department of Energys Initiatives<br />
for Proliferation Prevention (IPP) program. IPP was established in 1994 as a non-proliferation program of DOE / National Nuclear<br />
Security Administration and receives its funding each year through Congressional appropriation. The primary objective of IPP is<br />
to engage former Soviet nuclear weapons scientists, currently or formerly involved with weapons of mass destruction, in peaceful<br />
and sustainable commercial activities.<br />
Argonne National Laboratory provides management oversight for this project. More than 60 former weapons scientists are<br />
engaged in this project.<br />
With the project entering its mid-point, the emphasis is now on expanding the experimental work to include the sub-sites of<br />
Seversk (SCC), Zheleznogorsk (MCC) located in Siberia and Gatchyna (KRI) and applying the polymer technology to actual problematic<br />
waste streams. Work to date includes the solidification of over 100 waste streams for the purpose of evaluating all aspects<br />
of the polymers effectiveness with LLW and ILW complex waste. Waste…<br />
4) PRE-TREATMENT OF ORGANIC LIQUID WASTE STREAM AT CERNAVODA NPP (w/oP-59079)<br />
Gabriela Teodorov, Laszlo Toro, Adina Sandru, MATEFIN; Dennis Kelley, Pacific Nuclear Solutions;<br />
Dorin Dumitrescu, NPP Cernavoda (Romania/ USA)<br />
The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) was designed to maintain acceptable levels<br />
of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation.<br />
During the ten years operation of the Cernavoda NPP, a series of waste streams have been developed for waste management<br />
purpose. Some of these streams consist of radioactive organic liquid wastes: spent oils, spent solvents, liquid scintillation cocktails<br />
(LSC), flammable solids (solid-organic liquid mixture) and sludge.<br />
Effective treatment of organic liquids waste from the initial to the final stage has been a challenge for NPP Cernavoda. All components<br />
of the organic liquid waste stream have been stored in liquid form in stainless steel drums in the Solid Radioactive Waste<br />
Intermediate Storage Facility (SRWISF). This facility was originally designed for solid wastes only, consequently, the regulatory<br />
body has asked Cernavoda NPP to remove the flammable liquids from this repository as soon as possible.<br />
As a result, at the end of 2008, Cernavoda NPP initiated the solidification of organic liquid wastes (both historical and fresh<br />
wastes) together with a separation of solids associated with the organic liquids. In accordance with terminology of the International<br />
Atomic Energy…<br />
5) TRANSPORT AND DEPOSITION PROPERTIES OF MODEL SLURRIES<br />
OF ONE AND TWO PARTICLE SPECIES (wP-59140)<br />
Hugh Rice, Simon Biggs, Michael Fairweather, James Young, University of Leeds, Leeds, (UK)<br />
The UK nuclear industry has in its inventory legacy waste in the form of complex, polydisperse and polydense suspensions,<br />
slurries and sludges in a variety of storage and transport vessels. This waste has been difficult to characterise because of radioactivity<br />
and limited accessibility, and containment and disposal of the waste presents a continuing challenge. Our objectives are to<br />
investigate the effect of mono- and bidisperse suspensions with a range of particle sizes and densities on the turbulence characteristics<br />
and transport and settling behaviour of slurries that are chosen to be analogues of those found on nuclear sites. Two versatile<br />
slurry pipe-flow loops of different diameters have been commissioned which can be operated over a large range of Reynolds numbers<br />
and are amenable to ultrasonic, optical and physical measurement methods. In addition, a variety of particle characterisation<br />
studies have been performed on the particle species that form the suspensions. In particular, the effect of settled beds on the flow<br />
112
Abstracts Session 43<br />
velocity and turbulence characteristics and of inter-species interactions in bidisperse suspensions has been investigated. Results of<br />
particle characterisation are presented, along with mean and turbulent velocity profiles over a range of Reynolds number and particle<br />
concentration. The implications of the work for waste processing within the industrial context will be discussed in the full<br />
paper.<br />
6) APPLICATION OF A NEW TECHNOLOGY FOR REPROCESSING OF WASTES WITHIN THE FRAMEWORK<br />
OF REHABILITATION OF URANIUM MINES OPERATED BY IN SITU LEACHING (wP-59403)<br />
Gagik Martoyan, Garik Nalbandyan, Lavrenti Gagiyan,<br />
AREV SI CJS Company; Gagik Karamyan, Artak Barseghyan, Gagik Brutyan, Ecoatom LLC (Armenia)<br />
It is essential the environmentally safe industrial production of nuclear fuel especially in the case of uranium extraction by In<br />
Situ Leaching, when the environment and the deep extraction of uranium are important problems. In the presented paper it is studied<br />
the feasibility of the application of an electrodialysis method for the deep extraction of uranium and radium from liquid (acid)<br />
streams. It is proposed to apply a new electrodialysis method to ensure the necessary extraction level of elements. In the same time<br />
the new method ensures the recycling of acids used in the process.<br />
7) A FULLY OPERATIONAL PILOT PLANT FOR ELIMINATING RADIOACTIVE<br />
OILS MIXED WITH CHLORINATED SOLVENTS (wP-59044)<br />
Albert Jacobs, William Everett, Dewdrops Company (France)<br />
Disposal of organic liquid waste has become an increasing issue for many nuclear sites. Existing disposal solutions such as<br />
incineration or super critical water techniques are not compatible with wastes containing chlorinated solvents or fluorine owing to<br />
corrosion problems. As an example several hundred cubic meters of lubricating oils mixed with trichloroethylene (TCE) or perchloroethylene<br />
(PCE) are stockpiled on several French nuclear sites. For several years Dewdrops has been developing an original<br />
combination of mineralization processes for waste oils and solvents particularly well suited to the nuclear field. The patented technology<br />
relies on the alternation of chemical and biological oxidation mechanisms. The oxidized organic material predominately<br />
forms carbon dioxide, water and inorganic salts. This paper details the procedure and the results obtained for a particular case at<br />
the Tricastin nuclear site of Areva NC (South France). The organic waste used in this study was a 85/15 v/v ratio mix of lubricating<br />
oil and TCE. The pilot plant build upon the technology has a daily treatment capacity of approximately 10 liters. In the first<br />
step the TCE is mineralized by the photo Fenton reaction. Using hydrogen peroxide with an ultraviolet regenerated iron catalyst,<br />
TCE is transformed to carbon dioxide, water and…<br />
8) ADSORPTION OF CESIUM RADIONUCLIDES BY THE COMPOSITE SORBENTS<br />
CARBON FIBER/TRANSITION METALS FERROCYANIDES (wP-59255)<br />
Irina Sheveleva, Veniamin Zheleznov, Svetlana Bratskaya, Valeriy Kuryavyi,<br />
Valentin Avramenko, Institute of Chemistry FEBRAS (Russia)<br />
Among various methods of cesium removal from aqueous solutions, sorption using transition metals (Ni, Zn, Cu, Fe) ferrocyanides<br />
is the most efficient method due to extremely high affinity of cesium ions to ferrocyanides. Preparation of selective sorbents<br />
by fixation of ferrocyanides crystals in porous matrix of natural clinoptilolite, synthetic zeolites, alumosilicates, and carbon<br />
materials is an efficient way to increase decontamination factors and reduce sorbents expenditure in treatment of 137Cs-containing<br />
wastewaters.<br />
It is known that the efficiency of transition metals ferrocyanides application depends on the crystal size being the highest for<br />
nanocrystals. Although nanocrystals are difficult to handle in a direct application, they can be used in composite materials. In this<br />
case two main problems arise: how to control the crystal size of transition metals ferrocyanides and how to fix them reliably in the<br />
supporting matrix.<br />
In this paper we suggest a new route to preparation of composite materials selective to cesium ions using transition metals ferrocyanides<br />
stabilized by siloxane-acrylate latexes. The size of transition metals ferrocyanides is controlled by the size of the latex<br />
particles and their stability is determined by ionization of polyacrylic acid carboxylic groups on the functionalized latex surface.<br />
These functionalized particles can be used as…<br />
SESSION 43 — SITING, DESIGN, CONSTRUCTION, AND OPERATION<br />
OF L/ILW DISPOSAL FACILITIES - PART 2 OF 2 (1.19)<br />
1) 20 YEARS OF OPERATION FOR CENTRE DE L’AUBE<br />
DISPOSAL FACILITY: LESSONS LEARNED (w/oP-59235)<br />
Patrice Torres, Laurent Schacherer, Franck Duret, Pascal Lecoq, Alain Delaplanche, Michel Dutzer, Andra (France)<br />
The presentation will show the evolution of the facility during thes 20 years: in terms of deliveries, of type of waste packages,<br />
in terms of lexibility to answer the needs of waste generators, in terms of disposal vault design. Lessons leanrd will be emphasized.<br />
It will provide information on the environmental monitoring of the facility.<br />
2) DEMONSTRATION TEST OF UNDERGROUND CAVERN-TYPE<br />
DISPOSAL FACILITIES FISCAL 2010 STATUS (w/oP-59180)<br />
Yoshihiro Akiyama, Kenji Terada, Nobuaki Oda, Tsutomu Yada,<br />
Takahiro Nakajima, Radioactive Waste Management Funding And Research Center (Japan)<br />
The underground cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity levels mainly generated<br />
from power reactor decommissioning and for part of transuranic (TRU) waste mainly from spent fuel reprocessing are<br />
designed to be constructed in a cavern around 100 meters below ground, and to employ an engineered barrier system (EBS) of a<br />
combination of bentonite and cement materials in Japan. In order to advance the feasibility study for this disposal, The Demonstration<br />
Test for Underground Cavern-Type Disposal Facilities has commissioned by Japanese government since fiscal 2005, and since<br />
fiscal 2007 a full-scale mock-up test facilities has been constructed under actual subsurface environment. The main objective of the<br />
113
Session 44 Abstracts<br />
test is to establish construction methodology and procedures which ensure the required quality of the engineered barrier system<br />
(EBS) on-site. By fiscal 2010 some parts of the facilities has been constructed, and the test has demonstrated both practicability of<br />
the construction and achievement of the quality. They are respectively taken as low-permeability of less than 5E-13 m/s and lowdiffusion<br />
of less than 1E-12 m2 /s at the time of completion of construction. This paper covers the test results obtained by the construction<br />
of some parts of a bentonite and cement materials.<br />
3) DEMONSTRATION OF GAS PERMEABLE SEALS FOR RADIOACTIVE WASTE<br />
REPOSITORIES LABORATORY AND IN-SITU EXPERIMENTS (wP-59224)<br />
Joerg Rueedi, Paul Marschall, Nagra (Switzerland)<br />
In low/intermediate-level waste (L/ILW) repositories, anaerobic corrosion of metals and degradation of organic materials produce<br />
hydrogen, methane, and carbon dioxide. Gas migration in a L/ILW repository is one of the processes evaluated in the safety<br />
assessment of deep geological disposal in low-permeability formations, in particular with respect to the development of gas pressures<br />
in the repository caverns which could negatively affect the host rock or the engineered barrier system (EBS). In order to<br />
restrict build-up of gas overpressures in the emplacement caverns, Nagra (National Cooperative for the Disposal of Radioactive<br />
Waste, Switzerland) has proposed design options aimed at increasing the gas transport capacity of the backfilled underground structures,<br />
compromising neither the low hydraulic conductivity nor the radionuclide retention capacity of the EBS (Nagra, 2008). They<br />
involve specially designed backfill and sealing materials such as high porosity mortars as backfill materials for the emplacement<br />
caverns and sand/bentonite (S/B) mixtures with a bentonite content of 20% to 30% for the seals themselves and for backfilling other<br />
underground structures. These increased gas permeability materials can supplement the gas flow that is expected to occur through<br />
the excavation damaged zone (EDZ) and avoid the creation of overpressures.<br />
Preliminary experimental studies have confirmed the gas…<br />
4) POST-IODINE PRODUCTION NORM REPOSITORY TECHNICAL DESIGN AND<br />
RECONSTRUCTION EXPERIENCE IN TURKMENISTAN (wP-59183)<br />
Alexander Gelbutovsky, Peter Cheremisin, Alexander Troshev, Alexander Egorov,<br />
Mikhail M. Boriskin, Mikhail Bogod, ECOMET-S (Russia)<br />
Continuous extraction of the iodine, bromine and other elements from the underground mineral waters at the Balkanabat<br />
Iodine and Khazar chemical plants (Turkmenistan) resulted in their territories NORM contamination and significant waste quantities<br />
formation. Sites radiation safety is the major issue. Usually there are no any radiation monitoring systems and staff providing<br />
personnel, population and environment radiation safety and negative influence elimination. The most dangerous sites are the ones<br />
which are situated in the Caspian Sea coastal area. In 2009 the remediation project was initiated to prevent NORM distribution and<br />
eliminate environmental threat. The project frame covers a number of preparation and design works, charcoal sorption shops demolition,<br />
territories remediation, production waste conditioning and transportation to the repository for further safe storage. For that<br />
purposes the repository has been built in the near-by natural hollow. In the given report the materials related to repository design,<br />
reconstruction and operations start are presented. The brief data on the facilities condition, contamination characteristics and waste<br />
quantities are indicated. It is shown that that the mechanical method has been chosen for contaminated materials collecting and disposal.<br />
Main demolition, remediation and transportation decisions, activities and results are mentioned also.<br />
SESSION 44 — DISPOSAL SITE AND WASTE FORM CHARACTERIZATION<br />
AND PERFORMANCE ASSESSMENT - PART 1 OF 2 (1.13)<br />
1) RADIOLOGICAL CHARACTERIZATION OF THE DUTCH INTERIM<br />
WASTE STORAGE FACILITY SITE (w/oP-59023)<br />
Jeroen Welbergen, COVRA; Leo P.M. Velzen, Nuclear Research and Consultancy Group (Netherlands)<br />
The Central Organization for Radioactive Waste (COVRA) in the Netherlands operates since 1993 in the south-west of the<br />
Netherlands a facility for treatment of radioactive waste including interim storage buildings for HLW, LILW and NORM wastes as<br />
calcinate and depleted uranium (U3O8 ). The site of the interim waste storage facility has a size of about 200,000 m2 and is situated<br />
close to the Dutch nuclear power plant Borssele and a large phosphate production plant.<br />
It is evident that the waste storage site is subjected at regular time intervals at non-intrusive radiological measurements (e.g.<br />
dose-rate and contamination) to detect elevated radiation levels. However, these radiological measurements have not yet been performed<br />
according to approaches as described in the Environment Radiation Site Survey Execution Manual EURSSEM or the Multi<br />
Agency Radiation Site Survey Inspection Manual MARSSIM .<br />
The aim of the paper is threefold, first to describe in detail the process how to apply EURSSEM and especially for fast nonintrusive<br />
multi radiological detection techniques with control measurements. Second aim is to present and discuss the analyze<br />
results and follow up actions. The third and last aim is to discuss the advantages and disadvantages of combining the analyze results<br />
of fast non-intrusive measurements…<br />
2) CLIMATE CHANGE IMPACTS ON THE DISPOSAL ENVIRONMENT:<br />
A CLIMATE ANALOGUE APPROACH (wP-59274)<br />
Bertrand Leterme, Dirk Mallants, SCK●CEN (Belgium)<br />
The Belgian Agency for Radioactive Waste and Enriched Fissile Materials (ONDRAF/NIRAS) aims to develop a surface disposal<br />
facility for L/ILW in Dessel (North-East of Belgium). The objective of this study is to provide estimates for the next few millennia<br />
of both infiltration through the planned earth cover and groundwater recharge in the vicinity of the Dessel site. Available predictions<br />
of future temperature and precipitation often extend until AD 2100 only (e.g. IPCC). To circumvent this data limitation,<br />
we use existing records of climatic analogue stations deemed representative of future climates in Belgium. The following climate<br />
114
Abstracts Session 45<br />
states are considered: DO (maritime temperate, present-day climate in Dessel), Cs/Cr (subtropical with dry summers/no rainfall seasonality),<br />
EO (cold without permafrost) and FT (cold with permafrost). Climate data is then used in 1-D modelling of the soil-plantatmosphere<br />
system to quantify infiltration through the earth cover and recharge to groundwater for a sequence of probable future<br />
climate states.<br />
Using criteria including altitude, distance to moisture source, and atmospheric circulation system, several analogue stations<br />
were selected for each climate state Cs/Cr and EO/FT. They provided time series (30 years) of meteorological observations that<br />
allowed calculating potential evapotranspiration and water balance components for soils overlying either the repository…<br />
3) MINERALOGICAL ANALYSES OF OLD (78 AND 98 YEARS) CONCRETE (wP-59093)<br />
Tomoko Ishii, Hitoshi Owada, Radioactive Waste Management Funding and Research Center;<br />
Hiroyuki Sakamoto, Masahito Shibata, Kumi Negishi, Taiheyo Consultant Co.,Ltd. (Japan)<br />
Because Ca-dissolution from cementitious material is thought as a source of the long-term alteration of the performance of<br />
radioactive waste repository, much research such as dissolution test had been carried out. Those research brought some calculation<br />
models for leaching of cementitious material such as Atkinson’s model. Those calculation models have been verified that the results<br />
represent the alteration of cementitious minerals and the composition of the leachate by many researches. By using these calculation<br />
models, many estimation calculation for long-term mineralogical alteration in repository, such as cementitious barrier system,<br />
cement-clay interaction and so on, were carried out and the performance change of the repository were evaluated. However, results<br />
of immersion test by using bulky cementitious material had often pointed out that the actual alteration of cementitious material<br />
might be slower than the results of estimation calculation. This difference might be due to the change of mass-transport characteristics<br />
in the bulky cementitious material and/or at interfaces with the other materials.<br />
In this study, mineralogical analyses of two types old concretes were carried out. Drilled cores were collected from under<br />
groundwater level of the foundations of rotary kiln of cement production factory. Both of these concrete were made from Japanese<br />
ordinarily cement…<br />
4) MODELING OF ALTERATION BEHAVIOR ON BLENDED CEMENTITIOUS MATERIALS (wP-59096)<br />
Hitoshi Owada, Tomoko ISHII, Radioactive Waste Management Funding and Research Center;<br />
Mayumi Takazawa, Hiroyasu Kato, Mitsubishi Materials Corporation;<br />
Hiroyuki Sakamoto, Taiheyo Consultant Co.,Ltd.; Masahito Shibata, Taiheyo Consultant Co., Ltd. (Japan)<br />
Weve been trying to set the realistic alteration model for carious cementitious materials. Imaginary settings of mineral composition<br />
calculated by using chemical composition of cement, such as Atkinss model, had been used for the alteration calculation<br />
of cementitious material. However, calculated values of the concentration for some elements such as Al and S in leachate had been<br />
different from experimental values. In our previous study, we had set the mineralogical alteration model by using an allocation to<br />
some hydrated cement minerals from an experimentally analyzed initial chemical composition of the cementictious materials, and<br />
by the setting of secondary generated minerals that considered the leaching of Ca. As the result, the change of Al and S concentration<br />
in simulated leachate had approached to that in actual leachate in the alteration calculation for ordinary portland cement<br />
(OPC) in groundwater.<br />
In this study, for development of an appropriate mineral alteration model for blended cementictious materials, batch type<br />
leaching experiments that used the crushed sample of blast furnace slag cement and the silica cement were done. Blast furnace<br />
slaggy cements that mixed OPC with the blast furnace slag of 70wt.% and 90wt.% were used. Similarly, the silica cement that<br />
mixed OPC with an amorphous…<br />
SESSION 45 — REPOSITORY PROGRAMS: SITE SELECTION & CHARACTERIZATION,<br />
UNDERGROUND RESEARCH LABS, ENGINEERING & GEOLOGICAL BARRIERS - PART 2 OF 2 (2.7)<br />
1) EBS BEHAVIOR IMMEDIATELY AFTER REPOSITORY CLOSURE IN A CLAY HOST ROCK:<br />
THE HE-E EXPERIMENT (MONT TERRI URL) (wP-59288)<br />
Irina Gaus, Nagra; Klaus Wieczorek, GRS; Juan Carlos Mayor, ENRESA; Kristof Schuster, BGR;<br />
Thomas Trick, Solexperts; José-Luis Garcia-Siñeriz, Aitemin; Benoit Garitte, CIMNE; Uli Kuhlman,<br />
TK Consult (Switzerland/Germany/Spain)<br />
The evolution of the engineered barrier system (EBS) of geological repositories for radioactive waste has been the subject of<br />
many research programmes during the last decade. The emphasis of the research activities was on the elaboration of a detailed<br />
understanding of the complex thermo-hydro-mechanical-chemical processes, which are expected to evolve in the early post closure<br />
period in the near field. It is important to understand the coupled THM-C processes occurring in the EBS during the early post-closure<br />
phase so it can be confirmed that the safety functions will be fulfilled. Especially, it needs to be ensured that unexpected<br />
process interactions during the resaturation phase (heat pulse, gas generation, non-uniform water uptake from the host rock) do not<br />
affect the homogeneity of the safety-relevant parameters in the EBS (e.g. swelling pressure, hydraulic conductivity, diffusivity).<br />
The 7th Framework PEBS project (Long Term Performance of Engineered Barrier Systems) is using in depth process understanding<br />
for constraining the conceptual and parametric uncertainties in the context of long-term safety assessment. In previous EUsupported<br />
research programmes remarkable advances have been made to broaden the scientific understanding of THM-C coupled<br />
processes in the near field around the waste canisters. However, the detailed thermo-hydraulic behaviour of a bentonite EBS in a<br />
clay hostrock in response to anticipated temperatures of up to 140°C, produced by HLW (and spent fuel) at the canister surface, has<br />
so far not been evaluated at a large scale. Furthermore, earlier THM experiments have shown that upscaling of thermal conductivities<br />
and its dependency on the water contents from the laboratory scale to a field scale needs further attention.<br />
115
Session 46 Abstracts<br />
2) PERFORMANCE ASSESSMENT MODELING FOR THE GEOLOGICAL SITING REGIONS FOR THE L/ILW<br />
AND HLW REPOSITORIES IN THE CONTEXT OF THE SWISS SITE SELECTION PLAN (wP-59306)<br />
Andreas Poller, Juerg Schneider, Piet Zuidema, Nagra; Johannes Holocher,<br />
Gerhard Mayer, AF-Consult Switzerland Ltd. (Switzerland)<br />
In Switzerland, the Nuclear Energy Law requires the disposal of all radioactive waste in deep geological repositories. The procedure<br />
for selecting the repository sites is defined in the Sectoral Plan for Deep Geological Repositories and consists of three stages.<br />
In Stage 1, the National Cooperative for the Disposal of Radioactive Waste (Nagra) proposed geological siting regions based on<br />
criteria relating to safety and engineering feasibility. As part of Stage 2, Nagra has to select at least one site within each siting region,<br />
to carry out a provisional safety analysis for each site and a safety-based comparison of the sites. In order to achieve these objectives,<br />
the state of knowledge of the geological conditions in the siting regions has to be sufficient to perform the provisional safety<br />
analyses. In October 2010, Nagra published a report which documents Nagra’s technical-scientific assessment of this precondition,<br />
based on a comprehensive list of processes and parameters relevant for safety and engineering feasibility. A part of this assessment<br />
consists of test calculations for the provisional safety analyses. This paper summarizes how the numerous test calculations<br />
have been identified, how the concepts of radionuclide release from the repository are implemented into numerical codes and how<br />
input data and results are organized in order to ensure transparency and traceability.<br />
3) INVESTIGATIONS OF THE POSSIBLE SEPARATION DISTANCE BETWEEN SPENT<br />
FUEL/HIGH-LEVEL WASTE AND A LOW/INTERMEDIATE-LEVEL WASTE REPOSITORIES<br />
DUE TO GAS AND HEAT GENERATION (wP-59220)<br />
Rainer Senger, John Ewing, Intera Inc. Swiss Branch; (Switzerland)<br />
This study is part of a generic investigation for the assessment of the required minimum distance between a Spent Fuel/High-<br />
Level Waste/ Intermediate-Level Waste (SF/HWL/ ILW) repository and a Low/ Intermediate-Level Waste (L/ILW) repository. For<br />
this, a large-scale numerical model was constructed to investigate the two-phase flow behavior for such a repository configuration<br />
in a low-permeability claystone formation. The modeling focused on the pressurization mechanisms associated with (a) resaturation<br />
of backfilled underground facilities, (b) thermal effects caused by heat generation from the SF/HLW canisters, and (c) gas generation<br />
from corrosion and degradation of different wastes in the L/ILW and ILW caverns and in the SF/HLW emplacement tunnels.<br />
The model accounts for gas generation from corrosion and degradation of both L/ILW and ILW wastes indicating decreasing<br />
rates with time, and from corrosion of the SF/HLW canisters characterized by a constant rate. Heat generation from radioactive<br />
decay of radionuclides of MOX/UO2 wastes is described by an exponential decay with time. The preceding operational phases of<br />
the different repository components were simulated representing the transient initial conditions for the post-closure phase.<br />
4) HYDRAULIC/MECHANICAL MODELING OF SMECTITIC MATERIALS FOR HMC ANALYTICAL<br />
EVALUATION OF THE LONG TERM PERFORMANCE OF TRU GEOLOGICAL REPOSITORY (wP-59090)<br />
Ichizo Kobayashi, Kajima Corporation; Hitoshi Owada,<br />
Tomoko Ishill, Radioactive Waste Management Funding and Research Center (Japan)<br />
Aiming at evaluation of the long term performance of TRU geological repositories, the HMC analytical method has been studied.<br />
In this phase of the research, which is for four years, the hydraulic/mechanical modeling of smectitic materials for HMC analyses<br />
has been studied. In this paper, especially, the new experimental methods for investigation of the hydraulic/mechanical behavior<br />
of smectitic materials were developed.<br />
For the hydraulic modeling, the measurement method of the specific surface area of compacted smectitic materials was developed<br />
using XRD. The results of the method were applied to the Kozeny-Carman law. Since the specific surface area represents the<br />
microstructure of smectitic materials such as degree of swelling, it was found that the Kozeny-Carman law using measured specific<br />
surface area of compacted smectitic materials was useful to evaluating the hydraulic performance of smectitic materials. Moreover,<br />
since the Kozeny-Carman law can take the alteration of content of pore water into consideration by not only a coefficient of<br />
viscosity but also change of specific surface area, the Kozeny-Carman law will be more suitable to chemical and mechanical couple<br />
analyses than ordinary Darcy’s law.<br />
SESSION 46 — NATIONAL AND INTERNATIONAL PROGRAMS FOR<br />
SPENT FUEL, FISSILE, TRU, AND HLW MANAGEMENT (2.2)<br />
1) IMPLICATIONS OF CO-EXISTING NATIONAL AND MULTINATIONAL GEOLOGICAL<br />
REPOSITORY DEVELOPMENT PROGRAMMES IN EUROPE (wP-59118)<br />
Neil A. Chapman, Charles McCombie, Arius Association; Ewoud Verhoef, Covra (Switzerland/Netherlands)<br />
The aim of this paper is to identify interactions between national and multi-national geological repository programmes that are<br />
potentially either beneficial or problematic, so as to avoid any unintended negative impacts on national or multinational programmes<br />
and to maximise mutual benefits wherever possible. Regional, multi-national cooperation on geological disposal is a topical<br />
issue at present at the IAEA and also in the EU, which has produced a new proposed Directive that explicitly allows agreements<br />
on sharing.<br />
Two extended tables in the paper identify and comment briefly on historic and current positive and negative perceptions of coexisting<br />
national and multinational geological disposal programmes. It would, we believe, be a positive message to the global<br />
nuclear community to know that leading national disposal programmes are interacting constructively with regional initiatives. The<br />
extensive experience already gained in national programmes could be very beneficial to new nuclear countries. In particular, it is<br />
crucial for all nuclear programmes that the new entrants develop credible, long-term waste management programmes, whether these<br />
be national, regional or dual-track. For global safety and security reasons, the nuclear community must move towards a situation<br />
where both national and shared programmes will co-exist and interact symbiotically.<br />
116
Abstracts Session 47<br />
2) REGULATION OF AGEING FACILITIES - THE UK REGULATORS PERSPECTIVE (wP-59353)<br />
Ryan Maitland, Unit 2G Nuclear Installations Inspectorate (UK)<br />
The UKs strategy for spent Magnox reactor fuel demands continued operation of the Magnox Reprocessing facility at Sellafield<br />
(located in the North West of England) to reprocess the remaining spent fuel in the shutdown Magnox reactor stations and<br />
fuel from the two remaining operational Magnox reactor stations, Wylfa and Oldbury. Safety, security, environmental, transport,<br />
energy and economic issues provide the initiative to continue reprocessing in ageing facilities that are prone to chronic operational<br />
and nuclear safety challenges. One of the responsibilities of the UKs Office for Nuclear Regulation is to regulate the safety of continuing<br />
Magnox Reprocessing Operations against relevant health and safety legislation; this largely non-prescriptive framework<br />
requires dutyholders to demonstrably reduce risk so far as is reasonably practicable.<br />
This paper articulates the often complex balances that have to be made to demonstrate compliance with safety law to sustain<br />
continued operation of ageing reprocessing facilities. This paper details how the UKs regulatory framework facilitates a flexible,<br />
proportionate and goal-setting approach to regulating operational facilities where it is difficult to satisfy relevant good practice or<br />
standards that would be expected of a modern facility. The challenges presented by regulation of ageing, operational facilities is<br />
analogous to those from legacy waste retrieval and decommissioning; this paper reflects the versatility of the UKs regulatory<br />
approach to these two different areas of the fuel cycle.<br />
3) ESTABLISHMENT OF RESEARCH AND DEVELOPMENT PRIORITIES REGARDING<br />
THE GEOLOGIC DISPOSAL OF NUCLEAR WASTE IN THE UNITED STATES AND<br />
STRATEGIES FOR INTERNATIONAL COLLABORATION (wP-59168)<br />
Mark Nutt, Argonne National Laboratory; Michael Voegele, Complex Systems LLC; Jens Birkholzer,<br />
Lawrence Berkeley National Laboratory; Peter Swift, Sandia National Laboratories;<br />
Jeff Williams, U.S. Department of Energy; Kevin McMahon, Sandia National Laboratories;<br />
Mark Peters, Argonne National Laboratory (USA)<br />
The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technologies (OFCT) has established<br />
the Used Fuel Disposition Campaign (UFDC) to conduct research and development (R&D) activities related to storage,<br />
transportation and disposal of used nuclear fuel (UNF) and high level radioactive waste (HLW).<br />
The U.S. has, in accordance with the U.S. Nuclear Waste Policy Act (as amended), focused efforts for the past twenty-plus<br />
years on disposing of UNF and HLW in a geologic repository at Yucca Mountain, Nevada. The recent decision by the U.S. DOE<br />
to no longer pursue the development of that repository has necessitated investigating alternative concepts for the disposal of UNF<br />
and HLW that exists today and that could be generated under future fuel cycles. The disposal of UNF and HLW in a range of geologic<br />
media has been investigated internationally. Considerable progress has been made by in the U.S and other nations, but gaps<br />
in knowledge still exist.<br />
The U.S. national laboratories have participated in these programs and have conducted R&D related to these issues to a limited<br />
extent. However, a comprehensive R&D program investigating a variety of storage, geologic media, and disposal concepts has<br />
not been a part of the U.S. waste management program since the mid 1980s because of its focus on the Yucca Mountain site. Such<br />
a comprehensive R&D program is being developed and executed in the UFDC using a systematic approach to identify potential<br />
R&D opportunities. This paper describes the process used by the UFDC to identify and prioritize R&D opportunities.<br />
4) THE CIGÉO GEOLOGICAL REPOSITORY PROJECT (wP-59265)<br />
Thibaud Labalette, Alain Harman, Marie-Claude Dupuis, Andra (France)<br />
The future industrial geological repository Cigéo will provide France with a long term safe management solution for high level<br />
and long-lived intermediate waste produced by the French nuclear industry. According to the French Act of 28 June 2006, Andra<br />
carries out design studies so that the application can be examined in 2015 and, subject to licensing, the facility can be operated in<br />
2025.<br />
To be successful, the project must address issues related to local integration, industrial planning, safety and reversibility, while<br />
controlling costs. Andra is the guarantor of the balance between these concerns.<br />
A significant project milestone was reached in 2009 with the definition of an area of interest to locate the underground repository<br />
facilities. A new phase of dialogue with local actors is being performed to precise implementation scenarios of surface facilities.<br />
The site selection will be approved after a public debate planned for late 2012-early 2013.<br />
Cigéo will be an atypical nuclear facility, built and operated on over a hundred years. This long duration leads to develop repository<br />
facilities in successive operational phases. The characteristics of the first delivered waste packages will determine the investments<br />
by 2025 on the repository site as well as on waste production and interim storage sites.<br />
The underground repository facilities include specific features that cannot be simply transposed from current nuclear industry<br />
practices such as the co-activity between mining and nuclear operations, the ventilation and the fire risk management.<br />
SESSION 47 — RADIUM REMEDIATION HISTORICAL PERSPECTIVES<br />
AND CURRENT CIRCUMSTANCES - PART 2 OF 3 (4.47)<br />
1) PORT RADIUM START TO FINISH LIFE CYCLE: A CASE STUDY ON CANADA’S<br />
HISTORIC RADIUM/URANIUM MINE, INITIAL OPERATION AND CLOSURE, CONCERNS OF<br />
THE ABORIGINAL DENE PEOPLE, SUBSEQUENT ASSESSMENTS, REMEDIATION (wP-59332)<br />
Gerd Wiatzka, SENES Consultants Ltd. (Canada)<br />
Presentation by Steve Brown, SENES Consultants Ltd (USA)<br />
This paper provides a life study cycle case study on the historic Port Radium mine. In addition to the history of operations, it<br />
discusses the unique and successful approach used to identify the key issues and concerns associated with the former radium, uranium<br />
and silver mining property and the program activities undertaken to define the remedial issues and options that ultimately lead<br />
to the development of a preferred remedial plan. The Port Radium Mine site, situated approximately 275 km north of Yellowknife<br />
117
Session 47 Abstracts<br />
on the east shore of Great Bear Lake, Northwest Territories, was operated almost continuously between 1932 and 1982, initially for<br />
recovery of radium and uranium and subsequently for recovery of silver. Tailings production equalled an estimated 900,000 tons<br />
from uranium ore processing and 800,000 tons from silver processing operations. While the site was decommissioned at mine closure,<br />
site investigations were undertaken to address concerns expressed by residents of the community of Déline about residual contamination<br />
at the site and exposure of Déline residents as traditional land users and to identify residual environmental and safety<br />
issues based on current closure standards. Assessment of past radiation exposures of worker based on past practices associated with<br />
ore handling and concentrate shipping were also addressed. The paper provides insights into the approach and activities undertaken<br />
over a seven (7) year period that ultimately concluded with the final decommissioning of the site in 2007 and post remedial<br />
actions being carried out under the long term care and maintenance program.<br />
2) CHALLENGES IN DEVELOPING A REMEDIATION PLAN, PROCUREMENT PLAN<br />
AND LONG TERM MONITORING PROGRAM FOR THE FORMER PORT RADIUM URANIUM<br />
MINE THAT MEETS THE NEEDS OF THE COMMUNITY OF DELINE (w/oP-59333)<br />
Julie Ward, Indian and Northern Affairs Canada (Canada)<br />
After a five year political process to investigate historic and present day concerns about the former Port Radium Uranium Mine,<br />
the site has being remediated to present day standards. Prior to remediation Indian and Northern Affairs Canada (INAC) worked<br />
with Deline First Nations to develop a Remediation Plan that was suitable to the known environmental conditions and identified<br />
risks on site. Prior to remediation INAC obtained a land use permit and Waste Nuclear Substance Licence for the work that was<br />
carried out and for future storage of radioactive wastes. After the remediation plan was complete a procurement plan was developed<br />
for the work which followed Federal contracting polices, met the intent of the Sahtu Dene and Metis Comprehensive Land<br />
Claim Agreement and abided by INACs commitment under the Canada Deline Uranium Table to maximize local participation and<br />
subcontracting opportunities. Lastly, INAC worked with Deline to develop a monitoring plan in hopes to begin to restore their confidence<br />
in their environment while monitoring engineered remedial structures and residual risks on site.<br />
3) OVERVIEW OF RADIUM LEGACIES IN BELGIUM (wP-59367)<br />
Stephane Pepin, Koen Mannaerts, Boris Dehandschutter, André Poffijn, Ludo Jadoul,<br />
Walter Blommaert, Michel Sonck, FANC (Belgium)<br />
The Belgian metallurgical company, Union Minière, has been a key-player in the sector of radium production between 1922<br />
and 1969. The factory based in Olen has extracted radium from minerals and produced radium sources during that period. The radium<br />
production facilities have been dismantled in the 70s but legacies of the former production have still to be remediated. An<br />
overview of these legacies and of their radiological characteristics will be given.<br />
Next to the sites related to radium production, other radium legacies are related to NORM industries, essentially from the phosphate<br />
sector (phosphogypsum and CaF2 stacks).<br />
4) PREPARING FOR THE CONSTRUCTION PHASE OF THE PORT HOPE AREA INITIATIVE:<br />
CANADA’S LARGEST LOW-LEVEL RADIOACTIVE WASTE CLEAN-UP PROJECT (wP-59307)<br />
Christine Fahey, Andrea Denby, Glenn Case, Atomic Energy of Canada Ltd.;<br />
Tim Palmeter, Public Works Government Services Canada (Canada)<br />
The Port Hope Area Initiative (PHAI) is the largest clean-up of low-level radioactive waste (LLRW) ever undertaken in Canada.<br />
Situated within two adjacent Ontario municipalities, Port Hope and Clarington, the project scope includes the remediation of<br />
an estimated 1.7 million cubic metres (m3) of contaminated material and its consolidation within two new local waste management<br />
facilities in the form of above-ground, engineered containment mounds. The waste is primarily the by-product of uranium and radium<br />
ore processing activities of the former crown corporation Eldorado Nuclear Limited between 1932 and 1988.<br />
The PHAI is sponsored by the Government of Canada under the federal historic liabilities management program that is the<br />
responsibility of Natural Resources Canada (NRCan). Following the development of a new project execution framework in 2008,<br />
the PHAI Management Office, consisting of Atomic Energy of Canada Limited (AECL), Public Works & Government Services<br />
Canada (PWGSC) and NRCan staff, was established to perform the majority of Canadas obligations for the clean-up.<br />
The terms of reference for the PHAI are set out in a Legal Agreement signed in 2001 between the Government of Canada and<br />
the host municipalities. The Legal Agreement outlines a three-phased approach for the implementation of the PHAI:<br />
Phase 1 - planning and regulatory approvals; Phase 2 - remediation and construction; and Phase 3 - long-term monitoring and<br />
maintenance.<br />
118
Abstracts Session 48<br />
SESSION 48 — PANEL: RADIUM REMEDIATION - HISTORICAL PERSPECTIVES<br />
AND CURRENT CIRCUMSTANCES - PART 3 OF 3 (4.13)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 49 — PANEL: COMMUNICATIONS AND KNOWLEDGE MANAGEMENT - PART 1 OF 2 (5-21)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 50 — PANEL: COMMUNICATIONS AND KNOWLEDGE MANAGEMENT - PART 2 OF 2 (5-21)<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 51 — SAFETY CONSIDERATIONS ASSOCIATED WITH L/ILW MANAGEMENT (1.14)<br />
1) UK LLWR ENVIRONMENTAL SAFETY CASE SUBMISSION 2011 (wP-59135)<br />
Richard Cummings, LLWR Ltd; Andrew Baker, LLWR; Trevor Sumerling, LLWR;<br />
John Shevelan, Amy Huntington, LLWR Ltd. (UK)<br />
The UK’s Low Level Waste Repository Ltd submitted an Environmental Safety Case (ESC) for the disposal of low-level waste<br />
to the Environment Agency on the 1st of May 2011. The ESC is a major submission that will decide the future use of the Repository<br />
and has major implications for the success of the UK’s LLW Strategy and decommissioning programme. This paper provides<br />
an overview of the work that has been carried out to support the submission.<br />
Key aspects of this ESC include:<br />
detailed investigations of existing disposals, based on careful examination of existing records and other investigations, including<br />
interviews with former operational staff; analysis of uncertainties in future disposals; modelling of the biogeochemical evolution<br />
of the disposal system, which provides understanding of the evolution of pH, Eh and gas generation and thence underpinning<br />
for radionuclide releases in groundwater and gas; development of a 3-D groundwater flow model, calibrated against observed heads<br />
and with a detailed representation of the engineered features; analysis of coastal erosion and its impacts; a major focus on optimisation<br />
based on detailed technical studies; a conclusion that existing disposals do not require remediation; the choice of a concrete<br />
vault design with permeable side walls designed to avoid bathtubbing after the end of management control; a comprehensive set of<br />
assessment calculations, including thorough analysis of uncertainties, which demonstrate consistency with the Environment<br />
Agency’s risk and dose guidance levels; revision of the LLWR’s WAC, based in part on the use of the ‘sum of fractions’ approach;<br />
the use of a safety case document structure that emphasises key safety arguments in a Level 1 document and provides supporting<br />
evidence in a series of Level 2 documents; the provision of a Level 2 document that describes in detail how each aspect of the regulatory<br />
guidance has been addressed.<br />
2) AN ASSESSMENT OF THE RADIOLOGICAL IMPACT OF COASTAL EROSION<br />
OF THE UK LOW-LEVEL WASTE REPOSITORY (wP-59137)<br />
Trevor Sumerling, LLWR; Paul Fish, Halcrow Ltd.; George Towler, James Penfold, Quintessa Ltd;<br />
John Shevelan, Richard Cummings, LLWR Ltd. (UK)<br />
The UK Low Level Waste Repository Ltd submitted an Environmental Safety Case for the disposal of low-level waste to our<br />
regulator, the Environment Agency, on the 1st of May 2011. This includes assessments of the long-term radiological safety of past<br />
and future disposals.<br />
A particular feature of the Low Level Waste Repository (LLWR) is that, because of its proximity to the coast, the site is vulnerable<br />
to coastal erosion. Our present understanding is that the site will be eroded on a timescale of a few hundred to a few thousand<br />
years, with consequent disruption of the repository, and dispersal of the wastes.<br />
We have undertaken a programme of scientific research and monitoring to characterise the evolution and function of the current<br />
coastal system that provides a basis for forecasting its future evolution. This has included modelling of contemporary hydrodynamics,<br />
geomorphological mapping, repeat LiDAR and aerial photographic surveys to detect patterns and rates of change, coastal<br />
inspections and reconstructions of post-glacial (i.e. last 15,000 years) sea levels and sediment budgets. Estimates of future sealevel<br />
rise have been derived from international sources and consideration given to the impact of such on the local coastline. Two<br />
alternative models of coastal recession have then been applied, one empirical and one physical-process based, taking account of the<br />
composition of Quaternary-age sediments between the coast and the site and uncertainties in future local sea level change.<br />
3) DEVELOPMENT OF A METHODOLOGY FOR DETERMINING ILW PACKAGE<br />
MONITORING AND INSPECTION REQUIREMENTS (wP-59156)<br />
Jenny E. Morris, Timothy W. Hicks, Stephen M. Wickham, Galson Sciences Limited;<br />
Antonio Guida, Babcock International Group; Melanie Brownridge, James McKinney<br />
Darrell Morris, Nuclear Decommissioning Authority; Mark Tearle, Magnox Limited (UK)<br />
In the UK, monitoring and inspection is required by the regulators to ensure continued safe storage, retrievability and disposability<br />
of packages of radioactive waste in interim storage. Monitoring and inspection requirements may also be determined by any<br />
requirements for transport, further storage or disposal when the store is emptied. This paper presents an approach to establishing<br />
a monitoring and inspection strategy for stored intermediate level waste (ILW) packages that was developed under the UK Nuclear<br />
Decommissioning Authoritys Direct Research Portfolio programme.<br />
The key aspects to be considered when developing a package monitoring and inspection strategy are identified and used to<br />
develop a generic multi-stage process that will enable store operators to identify a justifiable monitoring and inspection strategy for<br />
ILW packages in long-term interim storage. Two spreadsheet tools have also been developed to facilitate use of the multi-stage<br />
process by store operators (IMPS - Inspection and Monitoring of Packages in Stores and CBAT - Cost / Benefit Analysis Tool).<br />
119
Session 51 Abstracts<br />
A statistically based methodology has been used to identify the number of waste packages to be inspected and an appropriate<br />
frequency of inspection, and aspects such as cost, risk and operational feasibility are taken into account.<br />
4) AN ASSESSMENT OF THE RADIOLOGICAL IMPACT OF HUMAN INTRUSION<br />
AT THE UK LOW LEVEL WASTE REPOSITORY (LLWR) (wP-59356)<br />
Timothy Hicks, Tamara Baldwin, Galson Sciences Ltd; Richard Cummings, LLWR Ltd.; Trevor Sumerling, LLWR (UK)<br />
The UK Low Level Waste Repository Ltd submitted an Environmental Safety Case for the disposal of low level waste (LLW)<br />
to the Environment Agency on the 1st of May 2011. The Environmental Safety Case (ESC) presents a complete case for the environmental<br />
safety of the Low Level Waste Repository (LLWR) both during operations and in the long term (Cummings et al, in these<br />
proceedings). This includes an assessment of the long-term radiological safety of the facility, including an assessment of the potential<br />
consequences of human intrusion at the site.<br />
The human intrusion assessment is based on a cautiously realistic approach in defining intrusion cases and parameter values.<br />
A range of possible human intrusion events was considered based on present-day technologies and credible future uses of the site.<br />
This process resulted in the identification of geotechnical investigations, a housing development and a smallholding as requiring<br />
quantitative assessment.<br />
A particular feature of the site is that, because of its proximity to the coast and in view of expected global sea level rise, it is<br />
vulnerable to coastal erosion. During such erosion, wastes and engineered barrier materials will be exposed, and could become targets<br />
for investigation or recovery. Therefore, human intrusion events have been included that are associated with such activities.<br />
5) FACTORS AFFECTING THE LONGEVITY OF INTERIM ILW STORES, MONITORING METHODS<br />
AND TECHNIQUES SUPPORTING STORE LIFE EXTENSION (wP-59151)<br />
Jenny E. Morris, Stephen Wickham, Timothy Hicks, Phil J. Richardson, Galson Sciences Limited; Melanie Brownridge,<br />
Darrell Morris, James McKinney, Nuclear Decommissioning Authority; Mark Tearle, Magnox Limited (UK)<br />
Life-limiting features of stores (i.e. components of a typical Intermediate Level Waste (ILW) store that are vulnerable to failure)<br />
can be separated into those related to store design, the continuing operation of the store and equipment and store management.<br />
Environmental factors, including temperature, humidity, atmospheric pollutants and radiation fields also affect the longevity of ILW<br />
storage buildings and the integrity of the waste packages within the store.<br />
The current condition of the store and the causes and rates of any observed deterioration need to be determined to estimate the<br />
current operating life of the store and to analyse the costs and benefits associated with life extension.<br />
Suitable monitoring techniques and methods for extending the operating life of stores, either by remediation or replacement of<br />
identified life-limiting features, have also been assessed. Techniques including visual inspection (directly or by use of CCTV or<br />
inspection cells), corrosion coupons, crane monitoring and a wide range of indirect measurement methods can be used to monitor<br />
the condition of life-limiting features and the store environment. Methods for extending store life include the application of paint<br />
or coatings to retard degradation, use of electro-chemical treatments and repair of the concrete structure or replacement of components.<br />
6) DIFFERENT TYPES OF RADIOACTIVE WASTE REPOSITORIES, EACH SUITED<br />
FOR A GIVEN TYPE OF RADIOACTIVE WASTE (wP-59293)<br />
Sylvie Voinis, Fabrice Boissier, Lise Griffault, Jean Louis Maillard, Michel Dutzer, Andra (France)<br />
The aim of this article is to present how Andra implements a dedicated solution per waste category. It relies on response to a<br />
series of questions concerning the appropriate waste disposal system such as: What type of radiological inventory is involved?<br />
What are the half-lives of the radionuclides and the associated timescales concerned for achieving the fundamental protection objective?<br />
.<br />
In that respect, Andra has developed and has implemented methods for all disposal facilities in order to reach common objectives:<br />
The immediate and long term protections of human beings and the environment constitute the fundamental objectives of all<br />
radioactive-waste disposal facilities.<br />
In order to achieve those protections, disposal facilities must be safe. Thus, Andra safety encompasses all design, implementation<br />
and operational measures for preventing risks of all kind internal, external during operation and after closure in consistency<br />
with defence in depth principles taken into account the peculiarity of waste disposal facilities: (i) balancing operational safety and<br />
post-closure safety, (ii) management of nuclear risks in underground repository for some of them, (iii) management of scientific<br />
understanding and related uncertainties, and (iv) management of long or very long- timescales.<br />
The presentation will illustrate Andras approach that has or will be conducted and will focus on communalities or peculiarities<br />
according to the type of waste and related disposal options regarding the following iterative steps: regulatory safety rules, input<br />
data, scenarios, safety assessments.<br />
SESSION 52 — DISPOSAL SITE AND WASTE FORM CHARACTERIZATION<br />
AND PERFORMANCE ASSESSMENT - PART 2 OF 2 (1.20)<br />
1) CHARACTERISATION OF THE GEOLOGY OF THE UK LOW LEVEL WASTE REPOSITORY (wP-59146)<br />
John Shevelan, LLWR Ltd; Nicholas Smith, National Nuclear Laboratory (UK)<br />
The UK Low Level Waste Repository Ltd (LLWR) submitted an Environmental Safety Case (ESC) for the disposal of lowlevel<br />
waste (LLW) to the UK Environment Agency on the 1st of May 2011. As part of the ESC, the LLWR have to demonstrate<br />
that a programme of site investigation and site characterisation has been carried out to provide the requisite information for the ESC<br />
and support facility design and construction. This paper explains the development of the site investigation programme and how the<br />
understanding of the geology of the site has developed.<br />
120
Abstracts Session 52<br />
The geological environment in the region of the LLWR consists of Quaternary age deposits overlying older bedrock. The site<br />
has been subjected to a series of site investigation programmes from 1939 to the present day. The development of 3-D geological<br />
models was necessary to integrate data from boreholes, trial pits, geophysical investigations and beach exposures and data gained<br />
from site operations.<br />
The understanding of the geology has developed with each new set of data. Early simple interpretations from a few boreholes<br />
have been superseded by a series of more complex interpretations each incorporating the increasingly detailed observations. Initial<br />
attempts to develop a lithostratigraphic representation of the geology proved difficult. It was also difficult provide a clear link<br />
between the geology and the hydrogeology using a lithostratigraphic approach as required for the development of hydrogeological<br />
models.<br />
2) IN-SITU INTERFEROMETRIC MEASUREMENTS OF COMPACTED SMECTITE<br />
UNDER HYPERALKALINE CONDITION (w/oP-59124)<br />
Hisao Satoh, Susumu Kurosawa, Mitsubishi Materials Corporation; Tomoko Ishii,<br />
Hitoshi Owada, Radioactive Waste Management Funding and Research Center (Japan)<br />
Alteration of bentonite buffer at the repository for radioactive waste is an unavoidable phenomenon. However, precise kinetic<br />
data is useful for evaluation of the endurance for long-term safety. Alkaline attack to bentonite by cement-leachates may enhance<br />
alteration of smectite into the other phase such as zeolite. Until recently, there are a number of detailed dissolution studies (e.g.,<br />
Cama et al., 2000; Yokoyama et al., 2005; Rozalen et al., 2008) for suspended smectite, using high precision measurements by ICP-<br />
MS and AFM analyses. In contrast, dissolution study of compacted smectite is very limited (e.g., Nakayama et al., 2003). In order<br />
to verify the previous data, the dissolution rate of compacted smectite with realistic density needs to be confirmed experimentally.<br />
We have, for the first time, applied in-situ vertical scanning interferometry (VSI) along with the auto-compaction cell for measuring<br />
dissolution rates of smectite compacted at 0.04-20.0 MPa and 70 ̊C in 0.3 M NaOH (pH12.1).<br />
At less-compaction (0.04 MPa), Kunipia-P smectite initially showed a relatively fast dissolution of ~2E-11 mol/m2/s which is<br />
comparable to the rate for suspended smectite under same pH-T condition. At high-compaction (
Session 53 Abstracts<br />
design, closure design, and quantitative assessments. Each of these issues requires an understanding of the movement of water<br />
through the facility and the surrounding geology during operations and following facility closure. Groundwater flow modelling has<br />
been used extensively in support of interpretation of field investigations, development of vault design, and assessment of the<br />
groundwater pathway as one of the major pathways by which contaminants may reach the environment. This paper describes these<br />
important aspects of the Environmental Safety Case.<br />
SESSION 53 — GLOBAL PARTNERSHIPS AND NATIONAL INITIATIVES IN<br />
ENVIRONMENTAL MANAGEMENT - PART 1 OF 2 (5.13)<br />
1) RUSSIAN NUCLEAR SUBMARINE ELIMINATION 2001 - 2011 BY THE<br />
INTERNATIONAL COMMUNITY (w/oP-59041)<br />
Michael Washer, Foreign Affairs and International Trade Canada; Alan Heyes, King’s College (Canada/UK)<br />
Following the 911 attack on the USA in 2001 the international community under Canadas G8 leadership established a $20 billion<br />
Global Partnership initiative to collaboratively address threats to global security posed by the proliferation and potential terrorist<br />
use of Weapons and Materials of Mass Destruction (WMMD) and related materials and knowledge. As an integral component<br />
of this initiative the international community agreed to assist Russia in advancing the elimination of its Cold War legacy of<br />
nearly 200 nuclear powered submarines left over from the collapse of the Soviet Union. This presentation presents an overview of<br />
the 10 years work that has now entirely eliminated that submarine legacy. The scale and complexity of the challenge along with<br />
each countrys contribution and approach is discussed along with key success factors and unique solutions adopted.<br />
2) THE GLOBAL PARTNERSHIP: ITS ACHIEVEMENTS, MISSED OPPORTUNITIES AND POTENTIAL TO<br />
ADDRESS FUTURE THREATS FROM THE SPREAD OF CBRN MATERIALS AND EXPERTISE (w/oP-59335)<br />
Alan Heyes, Wyn Bowen, Hugh Chalmers, King’s College (UK)<br />
In 2002, the G8 launched the Global Partnership (GP) against the Spread of Weapons and Materials of Mass Destruction. The<br />
partnerships budget was placed at $20 billion over 10 years, and it was supported by some 23 countries and the European Union<br />
(EU).Though it has had little public recognition, the partnership has been one of the G8s most successful initiatives and has led to<br />
many benefits, including improved international security and addressing a sizeable proportion of the Cold War nuclear and chemical<br />
weapons arsenal in the Former Soviet Union. Its future, however, remains undecided, as its funding is set to expire in less than<br />
two years.<br />
In 2009 and 2010 Kings College London with generous funding support from the US John D and Catherine T MacArthur<br />
Foundation, carried out a detailed evaluation of the achievements and benefits of the GP to date, its failings and lost opportunities,<br />
and potential future direction. Our findings indicate that the partnership has aided security in the Former Soviet Union and had a<br />
significant number of wider benefits with the potential to continue to do the same on a broader geographic level in future. As such,<br />
it is a valuable tool to assist the international community to work together to address global threats relating to chemical, biological,<br />
radiological and nuclear materials and related expertise and the G8 should take steps to renew its funding.<br />
3) THE GLOBAL THREAT REDUCTION INITIATIVES RADIOLOGICAL<br />
SECURITY COOPERATION WITH RUSSIA (wP-59361)<br />
Tiffany Blanchard, U.S. Department of Energy/National Nuclear Security Administration;<br />
William Abramson, Lawrence Livermore National Laboratory; James W. (J.R.) Russell, National Security Technologies;<br />
Catherine Roberts, Pacific Northwest National Laboratory (USA)<br />
The United States (U.S.) Department of Energy (DOE)/National Nuclear Security Administrations (NNSA) Global Threat<br />
Reduction Initiative (GTRI) supports both U.S. and international threat reduction goals by securing vulnerable nuclear and radiological<br />
material located at civilian sites throughout the world. GTRIs approach to reducing the threat posed by vulnerable, highactivity<br />
radioactive sources includes: removing and disposing of orphan or disused radioactive sources; implementing physical<br />
security upgrades at civilian sites containing radioactive sources; and establishing a cooperative sustainability program at sites to<br />
ensure that upgrades are maintained. For many years GTRI has collaborated successfully with the Russian Federation and international<br />
partners to improve radiological security in Russia. This paper provides a synopsis of GTRIs accomplishments and cooperation<br />
with Russia in the following areas: 1.) recovering and disposing of orphan and disused radioactive sources, 2.) recovering<br />
and disposing of radioisotope thermoelectric generators (RTGs), and 3.) providing physical security upgrades at civilian sites that<br />
contain vulnerable radiological material.<br />
4) KOLA PENINSULA RADWASTE MANAGEMENT IN THE FRAMEWORK OF THE ITALIAN-RUSSIAN<br />
COOPERATION AGREEMENT FOR GLOBAL PARTNERSHIP (wP-59392)<br />
Massimiliano Nobile, SOGIN (Russia)<br />
On the 5th of November 2003 a Cooperation Agreement, envisaging a grant of 360 Meuro in 10 years, was signed in Rome<br />
between Italy and Russia in the framework of Global Partnership <strong>Program</strong> launched by G8 at Kananaskis (Canada) in 2002. Funds<br />
availability was assured in March 2006.<br />
Competent Organizations are the Ministry of Economic Development for Italy and Rosatom for Russia. They act through a<br />
Steering Committee and a Project Management Unit, based in Moscow.<br />
So far, in five years of concrete work, 33 contracts have been signed and 145 Meuro have been spent.<br />
Together with other significant lines of activities, e.g. nuclear submarine dismantling, the management of waste, presently<br />
located at Andreeva Bay site, is surely the most important, not only for the amount of allocated funds (about half of available ones)<br />
but also for the urgency to solve serious environmental problems linked to the actual unsafe conditions of these waste, both as<br />
regards possible incidents and malicious attacks from outside.<br />
Volume of LL/IL waste at Andreeva Bay site are 17000 tons and 3000 tons, respectively for solid and liquid; moreover is<br />
expected, during the next 15 years, the production of additional 33000 tons of liquid and 8000 tons of solid, due to the need of<br />
demolishing existing facilities and final closing of the site.<br />
122
Abstracts Session 54<br />
5) SECURING OF THE SPENT NUCLEAR FUEL STORED ON GREMIKHA SITE - THE<br />
FORMER SOVIET SUBMARINE BASE IN NORTH-WEST OF RUSSIA (w/oP-59371)<br />
Alexandre Gorbatchev, CEA; Lucien Pillette-Cousin, AREVA TA: Boris Stepennov, NRC KI;<br />
Valery Eremenko, SevRAO; Anatoly Zakharchev, ROSATOM (France/Russia)<br />
In the framework of the G8 Global Partnership the French Commission on Atomic Energy (CEA) is in charge of the French<br />
funded projects aimed to secure the materials susceptible to be a subject of the proliferation or a malicious use. The securing of the<br />
Spent Nuclear Fuel (SNF) from the former soviet submarines is of a special importance for CEA and the Russian Rosatom. Our<br />
main bilateral project has focused on two kinds of the SNF (alpha cores and VVR assemblies) stored at Gremikha, the former submarine<br />
base in the North-West of Russia. As of 2011 a significant results have been achieved: 2/3 of VVR type assemblies have<br />
been removed from Gremikha and reprocessed at PO Mayak. Nine alpha cores are unloaded and stored on at Gremikha. The main<br />
task now is to prepare the removal from Gremikha of all the remaining SNF and also to set up the needed infrastructure at the sites<br />
where this SNF will be moved. Substantial funding and technical assistance both from France and Russia will be required for that.<br />
Beyond the operator of the Gremikha site (SevRAO), the CEA and Rosatom involve many expert organizations from both countries<br />
such as AREVA, Kurchatov Institute and many others. Their contribution is one of the key elements of the success.<br />
SESSION 54 — GLOBAL PARTNERSHIP IN ENVIRONMENTAL MANAGEMENT - PART 2 OF 2 (5.20)<br />
1) ENVIRONMENTAL AND RADIOLOGICAL REMEDIATION UNDER CANADA’S<br />
GLOBAL PARTNERSHIP PROGRAM 2004-11 (wP - 59185)<br />
Michael J. Washer, Foreign Affairs and International Trade Canada (Canada)<br />
Following the 911 attack on the USA in 2001 the international community under Canadas G8 leadership established a $20 billion<br />
Global Partnership initiative in 2002 to collaboratively address threats to global security posed by the proliferation and potential<br />
terrorist use of Weapons and Materials of Mass Destruction (WMMD) and related materials and knowledge. This major international<br />
initiative addressed four priority areas (1) Chemical Weapon Destruction (2) Nuclear powered submarine eliminations (3)<br />
Nuclear and radiological security; and (4) Employment for former weapon scientists. Additionally the Global Partnership initiative<br />
has addressed Biological Non-Proliferation. Canadas execution of all these program areas has resulted in substantial environmental<br />
benefits aside from the eradication and securing of WMMD. This paper will review specific environmental and radiological<br />
remediation achievements of all Global Partnership program areas addressed under Canadian funding 2004 through 2011.<br />
2) UK CONTRIBUTIONS TO THE DECOMMISSIONING OF THE BN-350<br />
REACTOR IN KAZAKHSTAN: 2002 – 2011 (wP-59099)<br />
Steven Laws, Department of Energy and Climate Change (UK), David Wells and Andrew Herrick, Nuvia Limited (UK)<br />
Since 2002, the UKs Global Threat Reduction <strong>Program</strong>me managed by the Department of Energy and Climate Change has provided<br />
assistance to the Republic of Kazakhstan with the decommissioning of the BN-350 sodium cooled fast reactor. Assistance<br />
has focused on non-proliferation, safety and security projects to ensure the permanent and irreversible shutdown of the reactor and<br />
the reduction of security, safety and environmental hazards, particularly those associated with the large inventory of liquid metal<br />
coolants (sodium and sodium-potassium alloy) and the presence of spent nuclear fuel (SNF). UK assistance efforts have been coordinated<br />
with those of the USA and have made use of the UKs experience in decommissioning its own fast reactor power stations,<br />
the Dounreay Fast Reactor (DFR) and the Prototype Fast Reactor (PFR).<br />
The paper describes work undertaken with UK technical and funding assistance support in the following areas:<br />
• Provision of training and technical support in project management and technical topics, including assistance with finalisation<br />
of the BN-350 Decommissioning Plan.<br />
• Liquid metal coolant treatment projects, including immobilisation of liquid products from the Sodium Processing Facility<br />
and processing of residual sodium remaining within the drained coolant circuits.<br />
• Immobilisation of highly active caesium traps, arising from sodium clean-up both during reactor operations and post-shutdown.<br />
• Operations to transfer the entire inventory of spent nuclear fuel from the reactor storage pond into dual-use storage and<br />
transport casks and then consign these casks to long-term secure storage remote from the reactor site. This activity was<br />
part of the major US-Kazakhstan SNF Storage Project.<br />
• Surveys of spent fuel route facilities to establish the absence of any significant amount of nuclear material.<br />
3) DISMANTLING OF CIVILIAN NUCLEAR POWERED FLEET TECHNICAL<br />
SUPPORT VESSELS. ENGINEERING SOLUTIONS (wP-59386)<br />
Konstantin Kulikov, Rinat Nizamutdinov, NIPTB Onega OAO (Russia)<br />
At the present time six nuclear technical support ships are under supervision of Atomflot FGUP. Two of them (Volodarsky<br />
FTB and Lepse FTB) were decommissioned and are berthing. One more ship Lotta FTB should be decommissioned during next<br />
two years.<br />
The nuclear technological support ships carrying SNF and radwastes appear to be a possible radiation contamination of Murmansk<br />
region and Kola Bay because the Ship long-term storage afloat has the negative effect on hull’s structures technical condition.<br />
As a result of this in the context of the Federal <strong>Program</strong> Nuclear and Radiation Safety (2008-2015) NIPTB Onega was engaged<br />
by state corporation Rosatom to develop the dismantling procedure for Volodarsky FTB and Lotta FTB.<br />
Developing of nuclear technological support ships dismantling projects the technical and economic assessment of dismantling<br />
was carried out. The following variants were examined: formation of SRW module for long-term storage at Saida Bay; complete<br />
dismantlement and allocation of all generated SRW into certified protective containers. The report contains description of variants,<br />
research procedure, comparative analysis of variants of dismantling of nuclear technological support ships with dismantling of<br />
nuclear submarine and propositions concerning further research of specified problem.<br />
123
Session 55 Abstracts<br />
4) PROGRESS IN INTERNATIONAL COOPERATION ON REGULATORY OF LEGACY MANAGEMENT:<br />
EXPERIENCE IN NORWEGIAN COOPERATION PROGRAMMES (wP-59399)<br />
Malgorzata Sneve, Norwegian Radiation Protection Authority (Norway)<br />
This paper describes the Norwegian Radiation Protection Authoritys (NRPA) experience in regulatory cooperation projects in<br />
Russia, with special focus on legacy issues. These legacies include many different kinds of objects and activities: obsolete large<br />
waste sources, such as those used in radioisotope thermoelectric generators; remediation of former military sites used for storage<br />
of spent nuclear fuel and radioactive waste; and wastes from uranium mining and ore processing. The objectives of these bi-lateral<br />
cooperation programmes are to promote effective and efficient regulatory supervision, taking into account international recommendations<br />
and good practice in other countries. Specific projects in the program address specific challenges which require practical<br />
local interpretation of ICRP recommendations, the IAEA Basic Safety Standards and other IAEA requirements and guidance<br />
documents. In some cases, new regulatory documentation has been required, as well as new regulatory procedures. In the long term,<br />
the program is intended to lead to an enhanced and enduring safety culture. The positive experience in Russia has encouraged the<br />
Norwegian government to extend the regulatory collaboration programme to countries in central Asia, using experience gained with<br />
Russian regulatory authorities as well as support from Russian Technical Support Organisations. The programmes are evolving into<br />
a regional regulatory support group. Noting this experience, the paper includes suggestions and ideas for how such regional groups<br />
can be effective in addressing common radiation safety objectives while addressing local differences in technical, geographical,<br />
economic and cultural matters in each country...<br />
5) METHODOLOGICAL AND PRACTICAL BASES OF PROVIDING INFORMATION SUPPORT TO<br />
ACTIVITIES ON ENVIRONMENTAL REMEDIATION OF THE SPENT NUCLEAR FUEL AND<br />
RADIOACTIVE WASTE TEMPORARY STORAGE FACILITY IN GREMIKHA (wP-59375)<br />
Dmitry Stepennov, Anatoly P. Varnavin, NRC Kurchatov Institute; Anatoly A. Zakharchev, Rosatom;<br />
Lucien Pillette-Cousin, AREVA TA (Russia/France)<br />
Remediation of a spent nuclear fuel (SNF) and radioactive waste (RW) temporary storage facility is a multifaceted process that<br />
includes a number of stages, such as development of a remediation programme, performance of comprehensive engineering and<br />
radiological survey, development of a remediation design, removal of SNF and RW up to the site cleanup. At any stage of the remediation,<br />
making of justified decisions is ensured by availability and completeness of associated information. Huge amount of information<br />
has to be managed. Therefore an information analysis system (IAS) was developed by the National Research Centre «Kurchatov<br />
Institute» within the framework of the project for environmental remediation of the SNF and RW temporary storage facility<br />
in Gremikha with financial and technical support provided by France (CEA) and the Russian Federation (Rosatom). The IAS<br />
accumulates all information about the project: technical and radiological characteristics of objects/facilities, cartographic information,<br />
documentation, data on the project participants, technologies and equipment involved. The IAS architecture includes the following<br />
functional subsystems: data management, data analytical processing, project management, geoinformation, 3D modeling,<br />
and public information. The IAS allows developers and performers of environmental remediation of the SNF and RW temporary<br />
storage facility in Gremikha to fulfill tasks arising at all stages of the work. The IAS operating experience can be transferred for<br />
use during surveys and remediation of any radiation hazardous facilities.<br />
SESSION 55 — SAFETY AND SECURITY RELATED TO ENVIRONMENTAL<br />
AND NUCLEAR MATERIALS MANAGEMENT (5.11)<br />
1) REMOTE RADIATION AND VISUAL SURVEYS OF THE HOT CELL WASTE VAULT<br />
AND SPENT FUEL TRANSFER ROUTE AT KAZAKHSTANS BN-350 REACTOR (wP-59101)<br />
David Wells, Nuvia Limited, Dorchester,United Kingdom, Collin Knight, Idaho National Laboratory;<br />
Alexander Klepikov, Nuclear Technology Safety Center; Igor Yakovlev, CRT&TD MAEC-Kazatomprom LLP;<br />
Evgeniy Tur, National Nuclear Center of the Republic of Kazakhstan; Andrew Herrick, Nuvia Limited (USA/Kazakhatan/UK)<br />
Kazakhstans BN-350 fast reactor was shut down in 1999 and is in the process of being decommissioned in preparation for Safestore.<br />
A key achievement during 2010 was the removal of the known inventory of spent nuclear fuel (SNF) from the reactor to offsite<br />
secure storage. As a complementary activity, surveys of areas of the fuel discharge route where it was considered possible for<br />
fuel pins or fuel residues to have collected over many years of operation were also arranged to confirm that no significant amounts<br />
of fuel of remained at the plant.<br />
This paper reports on the remote radiation and visual (video and still photograph) surveys undertaken on the following areas<br />
of the spent fuel route:<br />
• The waste storage repository or vault underneath the Post-Irradiation Examination Hot Cell in which non-destructive and<br />
destructive examination of irradiated fuels was undertaken throughout the operating life of the reactor.<br />
• The fuel transfer and washing cells within which irradiated fuel sub-assemblies were processed and residual sodium<br />
coolant removed.<br />
• The fuel storage ponds.<br />
Man access to several areas (particularly the waste vault) was not possible due to very high radiation levels from stored ??active<br />
wastes or residual contamination and in these cases specially engineered remote camera and detector deployment systems<br />
were developed and used. In other areas, such as the ponds, limited man access was possible under prepared and controlled conditions.<br />
124
Abstracts Session 56<br />
2) HUMAN RELIABILITY-BASED MC&A MODELING FOR EVALUATING<br />
THE EFFECTIVENESS OF PROTECTING NUCLEAR MATERIAL (wP-59379)<br />
Felicia A Durán, Gregory D. Wyss, Sandia National Laboratories (USA)<br />
Material control and accountability (MC&A) operations that track and account for critical assets at nuclear facilities provide a<br />
key protection approach for defeating insider adversaries. MC&A activities, from monitoring to inventory measurements, provide<br />
critical information about target materials and define security elements that are useful against insider threats. However, these activities<br />
have been difficult to characterize in ways that are compatible with the path analysis methods that are used to systematically<br />
evaluate the effectiveness of a sites protection system. The path analysis methodology focuses on a systematic, quantitative evaluation<br />
of the physical protection component of the system for potential external threats, and often calculates the probability, P(E),<br />
that the PPS is effective in defeating an adversary who uses that attack pathway. In previous work, Dawson and Hester observed<br />
that many MC&A activities can be considered a type of sensor system with alarm and assessment capabilities that provide reoccurring<br />
opportunities for detecting the status of critical items. This work has extended this characterization of MC&A activities as<br />
probabilistic sensors that are interwoven within each protection layer of the PPS. In addition, MC&A activities have similar characteristics<br />
to operator tasks performed in a nuclear power plant (NPP) in that the reliability of these activities depends significantly<br />
on human performance. Many of the procedures involve human performance in checking for anomalous conditions. Further<br />
characterization of MC&A activities as operational procedures that check the status of critical assets provides a basis for applying<br />
human reliability analysis (HRA) models and methods to determine probabilities of detection for MC&A protection elements...<br />
3) RISK-BASED SECURITY COST-BENEFIT ANALYSIS: METHOD AND EXAMPLE<br />
APPLICATIONS (w/oP-59381)<br />
Gregory Wyss, John Hinton, John Clem, Consuelo Silva, Felicia A Durán, Sandia National Laboratories (USA)<br />
Decision makers wish to use risk-based cost-benefit analysis to prioritize security investments. However, understanding security<br />
risk requires estimating the likelihood of attack, which is extremely uncertain and depends on unquantifiable psychological factors<br />
like dissuasion and deterrence. In addition, the most common performance metric for physical security systems, probability<br />
of effectiveness at the design basis threat [P(E)], performs poorly in cost-benefit analysis. It is extremely sensitive to small changes<br />
in adversary characteristics when the threat is near a systems breaking point, but very insensitive to those changes under other conditions.<br />
This makes it difficult to prioritize investment options on the basis of P(E), especially across multiple targets or facilities.<br />
To overcome these obstacles, a Sandia National Laboratories Laboratory Directed Research and Development project has<br />
developed a risk-based security cost-benefit analysis method. This approach characterizes targets by how difficult it would be for<br />
adversaries to exploit each targets vulnerabilities to induce consequences. Adversaries generally have success criteria (e.g., adequate<br />
or desired consequences and thresholds for likelihood of success), and choose among alternative strategies that meet these<br />
criteria while considering their degree of difficulty in achieving their successful outcome. Investments reduce security risk as they<br />
reduce the severity of consequences available and/or increase the difficulty for an adversary to successfully accomplish their most<br />
advantageous attack...<br />
SESSION 56 — ADVANCED L/ILW TECHNOLOGIES - PART 2 OF 2 (1.21)<br />
1) APPLYING FLUID DYNAMICS SIMULATIONS TO IMPROVE PROCESSING AND<br />
REMEDIATION OF NUCLEAR WASTE (wP-59172)<br />
Kelly J Knight, Jon M. Berkoe, Brigette M. Rosendall, L. Joel Peltier, Chris A Kennedy, Bechtel National (USA)<br />
Transport and processing of hazardous nuclear waste for treatment and storage can involve unique and complex thermal and<br />
fluid dynamic conditions that pose potential for safety risk and/or design uncertainty and also are likely to be subjected to more<br />
precise performance requirements than in other industries. From an engineering analysis perspective, certainty of outcome is essential.<br />
Advanced robust methods for engineering analysis and simulation of critical processes can help reduce risk of design uncertainty<br />
and help mitigate or reduce the amount of expensive full-scale demonstration testing.<br />
This paper will discuss experience gained in applying computational fluid dynamics models to key processes for mixing, transporting,<br />
and thermal treatment of nuclear waste as part of designing a massive vitrification process plant that will convert high and<br />
low-level nuclear waste into glass for permanent storage. Examples from industrial scale simulations will be presented. The computational<br />
models have shown promise in replicating several complex physical processes such as solid-liquid flows in suspension,<br />
blending of slurries, and cooling of materials at extremely high temperature. Knowledge gained from applying simulation has provided<br />
detailed insight into determining the most critical aspects of these complex processes that can ultimately be used to help guide<br />
the optimum design of waste handling equipment based on credible calculations while ensuring risk of design uncertainty is minimized.<br />
2) LIFETIME PERFORMANCE OF ASME AG-1 SECTION FK RADIAL FLOW FILTERS (wP-59170)<br />
CHARLES WAGGONER, Michael Parsons, Paxton Giffen, Mississippi State University;<br />
Jaime Rickert, Institute for Clean Energy Technology (USA)<br />
A series of 18 filters Section FK filters have been tested. This included testing two different configurations of 2000 cfm filters,<br />
12 remote change filters and 6 safe change filters. Testing consisted of lifetime performance evaluations using three different<br />
aerosol challenges and two different relative humidity/temperature conditions. Challenge aerosols ranged in mass median diameter<br />
(MMD) size from 500 nm (alumina) to 3000 nm (Arizona road dust). All testing was conducted consistent with NQA-1 standards.<br />
Test data were continuously collected for volumetric airflow, air temperature, relative humidity, up and downstream particle<br />
size distribution, up and downstream particle count, and filter differential pressure.<br />
Data provided in this paper include the mass versus differential pressure (dP) loading curves demonstrating loading capacity<br />
as a function of particle size. Results of mass loading are shown to follow current models for smaller aerosols, but large particle<br />
challenges demonstrated higher loading capacities than expected. Data will also be provided to demonstrate changes in the filter<br />
pack geometry during latter stages of loading (at differential pressures greater than 12-14 in. w.c. dP). This change in pleat geom-<br />
125
Session 57 Abstracts<br />
etry (pleat collapse) leads to a threshold dP at which the differential pressure will continue to increase even if aerosols are no longer<br />
added to the air flow. Data will be presented to demonstrate that reducing the airflow by 25 percent will counteract this runaway<br />
increase in dP, even if reduction of airflow is done as late as 25+ in. w.c. Filter failure for the units tested ranged from 30 to 50 in.<br />
wc...<br />
3) ALTERNATIVE STRATEGIES TO REDUCE COST AND WASTE VOLUME IN<br />
HEPA FILTRATION USING METALLIC FILTER MEDIA (wP-59348)<br />
Chris Chadwick, Porvair Filtration Group (UK)<br />
The disposal costs of contaminated HEPA and THE filter elements have been proved to be disproportionately high compared<br />
with the cost of the elements themselves.<br />
Work published elsewhere (Moore, et el 1992; Bergman et al 1997) suggests that the cost of use of traditional, panel type, glass<br />
fibre HEPA filtration trains to the DOE was, during that period, $29.5million, based on a five year life cycle, and including installation,<br />
testing, removal and disposal life cycle costs being based on estimates dating from 1987-1990.<br />
Within that cost estimate, $300 was the value given to the filter and $4,450 was given to the peripheral activity. Clearly, if the<br />
$4,450 component could be reduced, tremendous saving could ensue, in addition to the reduction of the legacy burden of waste volume.<br />
This issue exists for operators in both the US and in Europe.<br />
If HEPA filters could be cleaned to a condition where they could either be re-used or decontaminated to the extent that they<br />
could be stored as a lower cost wasteform or if HEPA/THE filter elements were available without any organic content likely to give<br />
rise to flammable or explosive decomposition gases during long term storage this would also reduce the costs and monitoring necessary<br />
in storage.<br />
4) ADVANCED DRYING SYSTEM TO MEET RADIOLYSIS CRITERIA OF METALLIC WASTE (wP-59116)<br />
Masamichi Obata, Yasushi Ooishi, Toshiba Corporation (Japan)<br />
High dose rate metal waste from core internals, such as BWR channel boxes or control rods are stored in fuel pool or site<br />
bunker pool. Waste form for final disposal of these high dose rate metal wastes should eliminate water to prevent hydrogen gas<br />
which can be caused by radiolysis of water. Toshiba’s newly developed drying system for high dose rate metal wastes enable very<br />
low content of water even if the waste have a powder layer. Toshiba will provide the total system to fabricate the waste form for<br />
high dose rate metal wastes.<br />
SESSION 57 — RECENT ADVANCES IN PROCESSING AND IMMOBILIZATION<br />
OF HLW, FISSILE AND TRU - PART 2 OF 2 (2.6)<br />
1) MITIGATION OF SLIDING MOTION OF A CASK-CANISTER BY FLUID-STRUCTURE<br />
INTERACTION IN AN ANNULAR REGION (wP-59208)<br />
Tomohiro Ito, Atsuhiko Shintani, Chihiro Nakagawa, Osaka Prefecture University;<br />
Kazuhisa Furuta, Osaka Prefcture University (Japan)<br />
Many spent fuels coming out of the nuclear power station are planned to be stored in the special site in Japan until they are<br />
reprocessed. In this site, the spent fuels are installed in a cylindrical container called canister. The canister, intern, will be installed<br />
in the outer cylinder called cask that is a free-standing structure. When this system is subjected to the strong seismic motions, sliding<br />
and rocking motions will be induced. And, in the worst case, the cask may collide to each other or overturn. Therefore, it is very<br />
important to reduce these motions of the cask in order to avoid the consequent contamination of radioactive substances.<br />
The authors have already conducted analytical investigations on the sliding and rocking motions of a cask-canister system subjected<br />
to a seismic excitation, and clarified the effects of the vibration of the inner canister. It was shown that the inner canister<br />
gives large influences on the sliding and rocking motions of the outer cask.<br />
In this study, we propose a mitigation method for sliding motion. Water is installed in an annular region between a cask and a<br />
canister. Fluid-structure interaction is taken into consideration for nonlinear sliding motion analyses. The effects of fluid-structure<br />
interaction on mitigation of sliding motions are studied. Furthermore, these effects are confirmed experimentally using a fundamental<br />
test model.<br />
2) IODINE CONDITIONING AS IODATE ION IN AN APATITE-LIKE CERAMIC (w/oP-59015)<br />
Lionel Campayo, CEA; Danielle Laurencin, Institut Charles Gerhardt De Montpellier;<br />
Agnès Grandjean, Institut De Chimie Séparative De Marcoule; Remy Delorme, CEA (France)<br />
Nuclear industry produces radionuclides like iodine-129 for which one of the management strategies could be an efficiently<br />
conditioning over a geological time scale. Several materials have been proposed to meet this objective. One of the most promising<br />
approaches consists in incorporating the element in robust inorganic matrices like apatites.<br />
Apatites are a large family of compounds of general formula M10 (XO4 ) 6Y2 (M = Ca2+, Sr2+, Pb2+&; XO4 = (PO4 ) 3-, (VO4 ) 3- &; Y = OH-, F-&). Iodine has been incorporated in apatites under the form of iodide anions (I-), in compounds like<br />
Pb10 (VO4 ) 4 . 8 (PO4 )1.2I2 which exhibits a good chemical resistance to the leaching by water. However, the number of apatite compositions<br />
able to incorporate iodine as iodide is limited. Recently, we have started to develop a new way of incorporating iodine in<br />
hydroxyapatite structures (M10 (PO4 ) 6 (OH) 2 , M = Ca or Sr) under mild conditions, using iodate anions (IO3 )-.<br />
Here, the synthesis and characterization of these new iodate-substituted apatite phases will be presented. Their thermal stability<br />
and their resistance to leaching will be described, revealing promising properties in view of radioactive iodine confinement<br />
applications.<br />
126
Abstracts Session 57<br />
3) STATUS OF THE DEVELOPMENT OF IN-TANK/AT-TANK SEPARATIONS TECHNOLOGIES<br />
FOR HIGH-LEVEL WASTE PROCESSING FOR THE U.S. DEPARTMENT OF ENERGY (wP-59109)<br />
Bill Wilmarth, SRNL; Nicholas P. Machara, US DOE Office of Technology Innovation and Deployment;<br />
Steve P. Schneider, US DOE Office of Waste Processing; Reid A. Peterson, PNNL;<br />
Sheryl R. Bush, SRNL (USA) Presentation by Jim Marra, US DOE (USA)<br />
Within the U.S. Department of Energys (DOE) Office of Technology Innovation and Development, the Office of Waste Processing<br />
manages a research and development program related to the treatment and disposition of radioactive waste. At the Savannah<br />
River (South Carolina) and Hanford (Washington) Sites, approximately 90 million gallons of waste are distributed among 226<br />
storage tanks (grouped or collocated in tank farms). This waste may be considered to contain mixed and stratified high activity and<br />
low activity constituent waste liquids, salts and sludges that are collectively managed as high level waste (HLW). A large majority<br />
of these wastes and associated facilities are unique to the DOE, meaning many of the programs to treat these materials are firstof-a-kind<br />
and unprecedented in scope and complexity. As a result, the technologies required to disposition these wastes must be<br />
developed from basic principles, or require significant re-engineering to adapt to DOEs specific applications. Of particular interest<br />
recently, the development of In-tank or At-Tank separation processes have the potential to treat waste with high returns on financial<br />
investment. The primary objective associated with In-Tank or At-Tank separation processes is to accelerate waste processing.<br />
Insertion of the technologies will (1) maximize available tank space to efficiently support permanent waste disposition including<br />
vitrification; (2) treat problematic waste prior to transfer to the primary processing facilities at either site (i.e., Hanfords Waste<br />
Treatment and Immobilization Plant (WTP) or Savannah Rivers Salt Waste Processing Facility (SWPF)); and (3) create a parallel<br />
treatment process to shorten the overall treatment duration...<br />
4) THE DEVELOPMENT, TESTING AND DEMONSTRATION OF A NEW CLASS<br />
OF INORGANIC ION SPECIFIC MEDIA EMPHASIZING THE OPTIMIZATION, STABILIZATION<br />
AND VOLUME REDUCTION OF THE FINAL NUCLEAR WASTE FORM (w/oP-59126)<br />
Mark Denton, Kurion Inc.; William D. Bostick, MCL, Inc. (USA)<br />
The primary focus of this paper is on the development of two novel classes of Ion Specific Media (ISM). However, it is important<br />
to note that these exclusively inorganic media were selectively designed to be compatible with advanced stabilization technologies<br />
(e.g., solidification and vitrification) and act as the final, stabilized waste forms required for storage or disposal on site. The<br />
purpose of developing such a class of high capacity and high specificity Ion Specific Media is to remove the recalcitrant isotopes<br />
(e.g., Cs-137, Sr-90,Tc-99 and I 129) during supplemental treatment (including Pretreatment, Off-Spec Tanks and Secondary Waste<br />
Treatment) and place them into very small packages for on-site storage, or HLW vitrification. These ISMs must also be a very stable<br />
form themselves for such potentially long-term, in-tank or dry storage (i.e.,inorganic in nature, leach resistant, non-hydrogen<br />
generating and amenable to future stabilization by thermal, or other, means).<br />
Having completed testing on a full spectrum of ISMs with these qualifications and ones that will selectively handle the prominent<br />
class drivers and recalcitrant isotopes in Commercial Nuclear Power Plants (NPPs) (e.g., Cs-137, Ni-63 and Sr-90), a further<br />
down select was done at our licensed facility, Materials and Chemistry Laboratories (MCL), in Oak Ridge, Tennessee for DOE specific<br />
isotope removal. This down select was carried out on batch reactors and columns at an analytical- and bench-scale on 1) near<br />
neutral pH surrogates and actual feeds, 2) secondary waste stream, pH ~8-9 surrogates, 3) strontium (Sr 90) removal from chelated<br />
tanks (weapons complex off-spec. tanks), and 4) high alkali tank Cs pretreatment, pH ~14. To further the efficacy testing here,<br />
prior to on-site hot-cell testing at a government facility, testing was also successfully carried out on actual Commercial Nuclear<br />
Power Plant waste streams, in both our Oak Ridge Lab as well as on site (including fuel pool and Boron Waste Storage Tank,<br />
BWST) waste waters.<br />
5) HIGH WASTE LOADING GLASS FORMULATIONS FOR HANFORD<br />
HIGH-ALUMINUM HLW STREAMS (wP-59388)<br />
Albert Kruger, US DOE (USA)<br />
The current estimates and glass formulation efforts have been conservative in terms of achievable waste loadings. These formulations<br />
have been specified to ensure that the glasses are homogenous, contain essentially no crystalline phases, are processable<br />
in joule-heated, ceramic-lined melters and meet WTP Contract terms. The WTPs overall mission will require the immobilization<br />
of tank waste compositions that are dominated by mixtures of aluminum (Al), chromium (Cr), bismuth (Bi), iron (Fe), phosphorous<br />
(P), zirconium (Zr), and sulfur (S) compounds as waste-limiting components. Glass compositions for these waste mixtures<br />
have been developed based upon previous experience and current glass property models. Recently, DOE has initiated a testing program<br />
to develop and characterize HLW glasses with higher waste loadings. Results of this work have demonstrated the feasibility<br />
of increases in waste loading from about 25 wt% to 33-50 wt% (based on oxide loading) in the glass depending on the waste stream.<br />
It is expected that these higher waste loading glasses will reduce the HLW canister production requirement by about 25% or more.<br />
Refractory components, such as crystalline alumina (corundum) or zirconia (baddeleyite) slow down the melting of glass<br />
batches in continuous melters. This effect can be considerable. Gibbsite and boehmite are common minerals found in high-level<br />
wastes.<br />
6) THE DESIGN, DEVELOPMENT AND DEMONSTRATION OF A NEW MODULAR VITRIFICATION<br />
SYSTEM (MVS®) FOR THE TREATMENT OF NUCLEAR WASTE (w/oP-59127)<br />
Mark Denton, Gaetan Bonhomme, Kurion Inc. (USA)<br />
The design and performance capabilities, of the Modular Vitrification System (MVS®), together with the latest results of<br />
experimental tests, is herein described. The MVS® is a novel heat treatment system in which nuclear waste can be processed directly<br />
inside the single-use, final disposal container. The MVS® single-use module consists of an outer canister, typically to be made<br />
of stainless steel specified by the clients site and by the waste acceptance criteria of waste repositories, and an inner induction susceptor/crucible,<br />
typically made out of graphite, which can be thermally insulated from the outer stainless canister. The inner crucible<br />
is inductively heated to the appropriate temperature, from 800°C (low melting point glasses) to up to 1550°C, by an external<br />
low frequency, alternating current (AC), water-cooled induction coil. The very wide range of operating temperatures, the independ-<br />
127
Session 58 Abstracts<br />
ence of melter to the chemistry of the waste and glass (e.g., conductivity) and the fact that parts exposed to high temperature molten<br />
glass are single-use, significantly decreases pre-treatment needs and permits making a wide range of vitrified products from borosilicate<br />
glass to iron phosphate glass. Moreover, technology development cycles and deployment are much faster and less costly on a<br />
single-use system designed to work for only a few hours at high temperatures in extreme conditions as compared to approximately<br />
5 years for incumbent technologies.<br />
SESSION 58 — D&D RADIOLOGICAL CHARACTERIZATION AND MONITORING (3.5)<br />
1) QUANTIFYING TC-99 CONTAMINATION IN A FUEL FABRICATION PLANT (wP-59024)<br />
Pete Burgess, Nuvia Ltd; Carol Darbyshire, Springfield Fuels Ltd (UK)<br />
The need was to quantify contamination in a large redundant building at the Springfields fuel manufacturing facility. The aim<br />
was to be able to identify any areas where the bulk activity exceeded 0.4 Bq/g Tc-99 as this would preclude the demolition rubble<br />
being sent to the local disposal facility. The problems associated with this project were the presence of significant uranium contamination,<br />
the realisation that both the Tc-99 and the uranium had diffused into the brickwork to a significant depth and the relatively<br />
low beta energy of Tc-99. The uranium was accompanied by Pa-234m, an energetic beta emitter.<br />
The first decision was to set up standard beta contamination monitors in an unusual way which minimised the response to other<br />
nuclides present while leaving the response to Tc-99 unchanged. The response of the monitor was then determined for Tc-99 activity<br />
buried at different depths. This could then be folded with any known concentration/depth profile to produce a response in<br />
counts/s/Bq/g. The concentration/depth profile was determined for several areas on the plant for Tc-99 and for uranium. The radiochemical<br />
analysis was performed locally but the performance of the local laboratory was checked during the initial investigation<br />
by splitting samples three ways and having confirmation analyses performed by 2 other laboratories. The results showed surprisingly<br />
consistent concentration gradients for Tc-99 and for uranium across the samples but the Tc-99 was clearly more “sticky” than<br />
the uranium.<br />
2) THE SCIENCE, ASSAYING AND WASTE SENTENCING OF ACTIVATED BIOSHIELDS (wP-59038)<br />
Ian Adsley, Nuvia Limited (UK)<br />
This paper describes the design and operation of the Combined Technology Automated Waste Characterisation System (CTA-<br />
WCS) at JRC Ispra. The WCS was designed for the measurement of fission products and uranium and plutonium containing waste<br />
arising from nuclear fuel and nuclear materials processing and reactor operations. The WCS covers a range of activity including<br />
Low and Intermediate Level Waste (LLW and ILW). The system is designed to measure the waste in 200 and 400 (440) litre drums<br />
with a maximum drum weight of 1500 kg. Gamma-ray measurements of radio-nuclide content are performed by a gamma ray<br />
measurement station which functions as either a Segmented Gamma Scanner (SGS) or Tomographic Segmented Gamma-ray Scanner<br />
(TSGS). Either of these two techniques may be employed to perform the functions of drum screening, non-destructive examination<br />
(NDE) and, where appropriate, final drum assay. Coupled to the gamma ray station is a surface dose-rate measurement station,<br />
which employs 6-shielded Geiger-Muller detectors. Active and passive neutron measurements are performed by an advanced,<br />
graphite lined Differential Die-away (DDA) system, which comprises the neutron measurement station.<br />
The DDA performs conventional passive neutron totals, coincidence, and multiplicity counting and active DDA total neutron<br />
counting. Data analysis is based on the use of a range of matrix calibrations, some determined by Monte Carlo analysis. Linking<br />
the gamma ray and neutron measurement stations is an automated roller conveyor with a 20 drum buffer capability and a weight<br />
measurement station. Drums are identified by bar code reading technology...<br />
3) GAMMA-RAY IMAGING FOR GENERATING 3D DOSE RATE MAPS (wP-59123)<br />
Karl Hughes, Edmund Cracknell, Babcock International Group (UK)<br />
The use of gamma-ray imaging has become established in the nuclear industry, especially in the fields of decommissioning and<br />
clean-up, for identifying the origins of elevated gamma dose rates. Since their first use in the mid 1990s, gamma-ray imaging<br />
devices, such as the Babcock RadScan 800, have been used to produce colour overlay plots that indicate, in two dimensions, the<br />
locations and distribution of radioactive contaminants. This information is invaluable in helping project managers to plan clean-up<br />
and shielding activities, ensuring that all work carried out is cost effective and ALARP. Recent work undertaken by Babcock<br />
demonstrates the capability to generate 3D maps of dose rate fields from the output of gamma-ray imaging work. The combination<br />
of gamma-ray imaging survey and resultant dose map is a very powerful tool for planning decommissioning. The conventional<br />
gamma-ray image provides an unambiguous identification of the origins of the dose rates present whilst the 3D dose map allows<br />
the dose uptake to personnel to be determined. Furthermore, the ability to quantify the effect of clean-up or shielding on the dose<br />
rates is possible, providing project teams with a metric for determining the best option available.<br />
4) SAMPLING VS. TAKING SOME (wP-59349)<br />
Dominique Francois-Bongarcon, AGORATEK International Consultants (Canada)<br />
The problem of sampling in general, and for nuclear decontamination in particular, is properly defined. A theory is presented<br />
(Gy’s Theory of Sampling, a.k.a. TOS) that brings all the answers and allows us to put them to work.<br />
The author draws from his lifelong experience in research, teaching and practical applications in this domain to emphasize the<br />
critical odds (i.e. risks) of not taking sampling explicitly into account when assessing grades and concentrations.<br />
The evolution of the acceptance of this theory in the nuclear industry is finally illustrated, and a hopeful glimpse into the future<br />
concludes the presentation.<br />
128
Abstracts Session 58<br />
5) WASTE ASSESSMENT: A PRACTICAL APPROACH TO PROVING WASTE METALS SUITABLE<br />
FOR CONSIGNMENT AS RADIOLOGICALLY EXEMPT MATERIALS (wP-59266)<br />
Iain Carvel, RSRL; Richard D Gunn, Robin Strange, Christopher Orr, Babcock International Group (UK)<br />
B220 at Harwell was built as a Radiochemical Research and Development facility in the latter part of the 1940s. The facility<br />
has been operational since 1949 and has been extended several times, most notably the Plutonium Glove Box Wing in the 1950s<br />
and the Remote Handling Wing in the 1980s. Only the Remote Handling wing remains operational, processing Historic Waste<br />
which is being recovered from storage holes elsewhere on site. The remainder of the facility is undergoing progressive strip out and<br />
decommissioning. In the Plutonium Wing and associated areas the waste fingerprint (nuclide vector) consists predominately of<br />
alpha emitting radionuclides.<br />
Decommissioning and Decontamination (D&D) operations often result in the production of large volumes of scrap metal waste<br />
with little or no radioactive contamination. Proving that the waste is clean can be costly and time consuming, as the shape and size<br />
of the metallic waste items often means that it is difficult or impossible to monitor all surfaces using conventional hand-held survey<br />
meters. This is a particular problem for alpha contamination measurement.<br />
Traditional radiological surveying techniques are very labour intensive and involve surveyors checking every surface using<br />
hand held instruments and smear sampling the hard to access areas. Even then 100% monitoring cannot be guaranteed.<br />
6) DEVELOPMENT OF A COMPUTER SYSTEM FOR SUPPORT AND DOCUMENTATION<br />
OF CLEARANCE OF BUILDINGS OF NUCLEAR INSTALLATIONS (wP-59278)<br />
Christoph Winkler, Stefan Woerlen, Stefan Thierfeldt, Frank Schartmann, Brenk Systemplanung (Germany)<br />
Clearance of buildings of nuclear installations in Germany has to comply with general requirements laid down in Section 29<br />
of the German Radiation Protection Ordinance (RPO; Strahlenschutzverordnung), clearance levels as stipulated in Table 1 of Annex<br />
III RPO and technical guidance given in the technical standard DIN 25457. Clearance procedures are usually proposed by the<br />
licensee and are made part of a decommissioning licence after appropriate review by the authorities. The clearance procedures consist<br />
of a radiological characterisation of the various parts of the buildings, a decontamination step if necessary, followed by measurements<br />
for checking the success of decontamination, and the actual decision measurements for demonstrating compliance with<br />
clearance levels.<br />
These three steps rely on various measurement methods, selected depending on the relevant radionuclides to be measured, like<br />
sampling with subsequent gamma spectrometry (and if necessary separate evaluation of beta and alpha emitting nuclides), measurements<br />
with surface contamination monitory and in situ gamma spectrometry. For a nuclear power plant, the number of samples<br />
taken during this procedure can easily reach a few 10,000, while the number of single measurements can reach several 100,000 single<br />
surface measurements and several 10,000 measurements with in situ gamma spectrometry. This large number of data together<br />
with the correct interpretation according to the valid nuclide vector, the penetration depth of the contamination, the correction for<br />
radioactive decay etc have to be managed, which is a error-prone process if carried out manually or with insufficient support by<br />
customised software.<br />
7) GEOSTATISTICAL METHODOLOGY FOR WASTE OPTIMIZATION<br />
OF CONTAMINATED PREMISES (wP-59344)<br />
Yvon Desnoyers, GEOVARIANCES; Didier Dubot, CEA/FAR/USLT/SPRE/SAS (France)<br />
At the end of process equipment dismantling, the complete decontamination of nuclear facilities requires the radiological<br />
assessment of residual activity levels of building structures. As stated by the IAEA: Segregation and characterization of contaminated<br />
materials are the key elements of waste minimization.<br />
From this point of view, the set up of an appropriate evaluation methodology is of prime importance. The radiological characterization<br />
of contaminated premises can be divided into three steps. First, the most exhaustive facility analysis provides historical<br />
and qualitative information. Then, a systematic (exhaustive or not) control of the radiation signal is performed by means of in situ<br />
measurement methods such as surface control device combined with in situ gamma spectrometry. Besides, in order to assess the<br />
contamination depth, samples can be collected at several locations within the premises and analysed. Combined with historical<br />
information and radiation maps, such data improve and reinforce the preliminary waste zoning.<br />
The relevance of the geostatistical methodology relies on the presence of a spatial continuity for radiological contamination.<br />
In this case, geostatistics provides reliable methods for activity estimation, uncertainty quantification and risk analysis, which are<br />
essential decision-making tools for decommissioning and dismantling projects of nuclear installations.<br />
Besides, the geostatistical framework provides answers to several key issues that generally occur during the clean-up preparation<br />
phase: How to optimise the investigation costs? How to deal with data quality issues? How to consistently take into account<br />
auxiliary information such as historical inventory? How to integrate the remediation support into the modelling? How to quantify<br />
uncertainties in the remediation costs while computing contaminated volumes?<br />
8) DISCRIMINATION MONITORS FOR VARIOUS KINDS OF WASTE TO BE DOWN GRADED (wP-59117)<br />
Susumu Naito, Syuji Yamamoto, Mikio Izumi, Masamichi Obata, Yukio Yoshimura,<br />
Jiro Sakurai, Hitoshi Sakai, Toshiba Corporation (Japan)<br />
During operation and maintenance, or decommissioning of nuclear power plant, various kind of waste should be treated, and<br />
exposure control is also required. These wastes have a wide range of contamination, different composition of nuclides, and a different<br />
shape, so each measurement instrument would be optimized for its use especially for very low level radioactivity measurement.<br />
TOSHIBA provides appropriate equipment for any needs to discriminate the very low and non radioactive waste to save cost<br />
of waste disposal, based on our original and innovative technology. For alpha emitting nuclides, we are ready to supply instruments<br />
based on ionized particle measurement technology. For beta, gamma-emitting nuclides, we are ready to customize a shape of detector<br />
based on our original plastic scintillation material. Some examples will be introduced.<br />
129
Session 59 Abstracts<br />
SESSION 59— RISK/PERFORMANCE ASSESSMENTS AND CONTAMINANT MIGRATION (4.7)<br />
1) UNCERTAINTIES ON THE EXTENSION OF A POLLUTED ZONE (wP-59198)<br />
Chantal de Fouquet, Mines ParisTech - Ecole des mines de Paris (France)<br />
Data collected during the sampling of polluted sites are mainly used to characterize the concentration level and, through an<br />
exploratory and variographic analysis, to characterize the spatial variability; at fixed support, to estimate the concentrations in order<br />
to trace pollution map. In the case of kriging, this map is completed by the map of the standard deviation of the estimation error,<br />
making it possible to delimit the zones in which the estimation is considered to lack in precision. If a proportional effect is present<br />
(the local spatial variability depends on the local concentrations mean), the map of error standard deviation has to be corrected to<br />
take into account the increase of spatial variability with the local concentration mean.<br />
A confidence interval can be derived conventionaly from the kriging estimation and the associated error standard deviation.<br />
For a fixed limit threshold, the polluted site can then be divided in three areas: the polluted zone, at a fixed statistical risk; the not<br />
polluted zone, at a fixed statistical risk; the zone of uncertainty, in which the estimated concentrations are close to the threshold.<br />
Because of the estimation error, it is not possible to specify if the exact concentrations exceed or not the threshold.<br />
In the case of a soil pollution by hydrocarbons, usual and geostatistical forecasts are compared. The effective consequences of<br />
these various forecasts on the quality of the site remediation are quantified and discussed.<br />
2) IDENTIFICATION AND IMPLEMENTATION OF END-USER NEEDS DURING DEVELOPMENT<br />
OF A STATE-OF-THE-ART MODELING TOOLSET (wP-59069)<br />
Roger Seitz, SRNL; Mark Freshley, PNNL; Susan Hubbard, Lawrence Berkeley National Lab;<br />
Mark Williamson, US DOE; Paul Dixon, LANL; Kurt Gerdes, DOE EM; Yvette Collazo , US DOE (USA)<br />
The U.S. Department of Energy (USDOE) Office of Environmental Management, Technology Innovation and Development is<br />
supporting development of the Advanced Simulation Capability for Environmental Management (ASCEM). ASCEM is an emerging<br />
state-of-the-art scientific approach and software infrastructure for understanding and predicting contaminant fate and transport<br />
in natural and engineered systems. The modular and open-source high performance computing tools will facilitate integrated<br />
approaches that enable standardized assessments of performance and risk for EM cleanup and closure decisions.<br />
Recognizing end-user needs and engaging end-users in the development process is expected to lead to better development and<br />
implementation of the toolsets in the user community. End-user involvement in ASCEM covers a broad spectrum of perspectives,<br />
including: performance assessment (PA) and risk assessment practitioners, research scientists, decision-makers, oversight personnel,<br />
and regulators engaged in the USDOE cleanup mission. The intent is to facilitate regular feedback between the scientists and<br />
modeling experts developing the tools and the practitioners and stakeholders in the field who will be implementing the tools for<br />
decision-making.<br />
End-users are engaged in ASCEM in three specific activities: User Steering Committee, user needs interface task, and demonstrations<br />
of the ASCEM tools. The User Steering Committee comprises management from USDOE Field Offices, USDOE Contractors,<br />
and regulatory bodies and is tasked with providing suggestions and feedback for the development team from a higher-level<br />
implementation perspective. The user needs interface task is targeted at gathering and documenting suggestions and feedback from<br />
practitioners and oversight personnel involved in day-to-day modeling, research and review activities at USDOE Sites. The demonstration<br />
activities involve application of developing ASCEM tools and capabilities for representative problems at DOE sites.<br />
3) URANIUM INVESTIGATION IN AN ALLUVIAL AQUIFER WITH DIRECT PUSH METHODS (w/oP-59281)<br />
Fabian De Weirdt, Geoprobe Environmental Technologies s.a. (Belgium)<br />
The U.S. EPA has established a maximum contaminant level of 30ug/l for uranium in drinking water due to its toxicity as a<br />
heavy metal. This regulation has affected many small public water supply systems in the US and several of them are struggling to<br />
come into compliance with the new standard. One such community is Clarks, NE, US which is situated on the alluvial deposits of<br />
the Platte River that are underlain by the Cretaceous Age Niobrara formation. Geoprobe Systems coordinated with the Nebraska<br />
Dept. of Health and Human Services, Water Well Stds. <strong>Program</strong> to investigate the cause of the elevated uranium in the groundwater<br />
that supplies drinking water to the village of Clarks.<br />
Initially hydraulic profiling tool (HPT) logs were obtained at selected locations across the Clarks well field. The HPT probe<br />
was advanced to depths of almost 36m (120ft) at several locations and the logs provided detailed information about the hydrostratigraphy<br />
of the local aquifer not available from the drillers logs. The HPT logs were used to guide selection of screen depths for<br />
small diameter wells that were installed with direct push (DP) methods. A total of nine wells were installed at two locations at the<br />
facility with well depths ranging from as little as 6m (20ft) to a maximum of 36m (118ft). All wells were grouted bottom-up with<br />
a tremie tube using 25% solids bentonite slurry to assure screen interval isolation.<br />
4) INDEPENDENT TECHNICAL REVIEWS FOR GROUNDWATER AND SOIL REMEDIATION<br />
PROJECTS AT US DEPARTMENT OF ENERGY SITES (w/oP-59188)<br />
Dawn Kaback, AMEC; Grover Chamberlain, DOE EM; John G. Morse, US DOE; Scott W. Petersen, CH2M Hill (USA)<br />
The Department of Energy Office of Environmental Management has supported independent technical reviews of soil and<br />
groundwater projects at multiple DOE sites over the last 10 years. These reviews have resulted in significant design improvements<br />
to remedial plans that have accelerated cleanup and site closure. Many have also resulted in improved understanding of complex<br />
subsurface conditions, promoting better approaches to design and implementation of new technologies.<br />
Many of these reviews have been sponsored and coordinated through the Office of Technology Innovation and Development<br />
(OTID), whose mission is to promote the practical application of innovative technologies and approaches. Reviews have also been<br />
sponsored within the EM site cleanup program in concert with local regulators and stakeholders.<br />
130
Abstracts Session 59<br />
Independent technical reviews add value, because they provide another perspective to problem solving and act as a check for<br />
especially challenging problems. By bringing in a team of independent experts with a broad experience base, alternative solutions<br />
are recommended for consideration and evaluation. In addition, the independence of the panel can is significant, because it is able<br />
to address politically sensitive issues. The expert panel members typically bring lessons learned from other sites to help solve problems<br />
associated with their task at hand. However, their recommendations at a particular DOE site can often be applied at other DOE<br />
sites, because of the common nature of many of the problems, making the review potentially even more valuable.<br />
5) ADVANCED SIMULATION CAPABILITY FOR ENVIRONMENTAL MANAGEMENT (ASCEM) (wP-59065)<br />
Paul Dixon, LANL; Mark Williamson, US DOE; Mark Freshley, Pacific Northwest National Lab;<br />
David Moulton, LANL; Ian Gorton, Pacific Northwest National Laboratory; Elizabeth H. Keating, LANL;<br />
Yvette Collazo , US DOE; Kurt Gerdes, DOE EM; Juan Meza, Lawrence Berkeley National Laboratory (USA)<br />
The U.S. Department of Energy Office of Environmental Management, Technology Innovation and Development determined<br />
that the uniform application advanced modeling in the subsurface could potentially reduce the cost and risk associated with their<br />
environmental cleanup mission. In response to this determination, the EM office of Technology Innovation and Development,<br />
Groundwater and Soil Remediation (EM-32) began the program Advanced Simulation Capability for Environmental Management<br />
(ASCEM) in 2010. ASCEM is a state-of-the-art scientific tool and approach for understanding and predicting contaminant fate and<br />
transport in natural and engineered systems. The modular and open source high performance computing tool will facilitate integrated<br />
approaches to modeling and site characterization that enable robust and standardized assessments of performance and risk for<br />
EM cleanup and closure activities.<br />
The ASCEM initiative supports the reduction of uncertainties and risks associated with DOE-EMs environmental cleanup and<br />
closure programs by better understanding and quantifying the subsurface flow and contaminant transport behavior in complex geological<br />
systems. This includes the long-term performance of engineered components, including cementitious materials in nuclear<br />
waste disposal facilities that may be sources for future contamination of the subsurface. This paper, at a high level, will describe<br />
the ASCEM tools, approach, recent technical reports and programmatic accomplishments completed in 2010.<br />
6) A PHYSIOCHEMICAL ANALYSIS OF THE MECHANISMS FOR TRANSPORT AND<br />
RETENTION OF TECHNETIUM (TC-99) IN UNSATURATED SOILS (w/oP-59050)<br />
Danielle P Jansik, Dawn Wellman, Elsa Cordova, DeNomy Dage, PNNL;<br />
Dorthe Wildenschild, Oregon State University (USA)<br />
The transport of technetium (Tc-99), is of interest due to the potential for human exposure and impact on ecosystems. Technetium<br />
has been released to the environment through nuclear power production and nuclear fuel processing; as a result, further<br />
spreading of Tc-99 is a concern at DOE sites across the US. Specifically, technetium is a contaminant of concern at the Hanford<br />
Site in southeastern Washington, due to the magnitude of material that was disposed. The current body of work conducted on Tc-<br />
99 has provided a wealth of information regarding the redox relationships, sorption, solubility, and stability of the mineral phases<br />
(Artinger et al., 2003; Beals and Hayes, 1995; Cui and Eriksen, 1996b; Gu and Schulz, 1991; Jaisi et al., 2009; Keith-Roach et al.,<br />
2003; Kumar et al., 2007), however little work has been conducted on the transport of technetium in unsaturated soils.<br />
Current conceptual models do not explain the persistence and presence of technetium in deep vadose zone environments such<br />
as the Hanford site. In an oxic reducing environment with low organic content the residence time of technetium is the soil would<br />
be expected to be low, due to its low sorption and high solubility. Surprisingly, nearly 50 years following the release of contamination<br />
into the site, much of the element has persisted in the subsurface. Using an integrated testing approach we examined the mechanisms<br />
for physical and chemical retention and transport of technetium. By employing transport and breakthrough curve analysis<br />
as well as pore water and sequential extractions, we evaluated transport behavior, technetium mineral association, and technetium<br />
leachability with regard to pore size distribution.<br />
7) INTERMEDIATE AND LONG-TERM RADIOLOGICAL CONSEQUENCES OF UNCONTROLLED<br />
SALINE SOLUTION ACCESS INTO ASSE MINE (wP-59163)<br />
Veronika Ustohalova, Christian Küppers, Öko-Institut e.V. (Germany)<br />
The Asse salt mine was used as a test site for radioactive waste disposal in salt formations between 1967 and 1978. At that<br />
time, low- and intermediate-level radioactive waste was placed in chambers at a depth of about 750 m and 511 m below ground.<br />
Due to geological conditions and anthropogenic activities, the mine is instable such that water penetrates into it. The main cause of<br />
the mines instabilities comes from a large volume of dead space in the form of drifts and chambers in the salt rock. This space is<br />
close to the adjoining rock. As a consequence, clefts in surrounding rocks have developed. Since 1988, salt-saturated groundwater<br />
has been leaking into the upper part of the southern flank of the mine. These instabilities create a high risk of mine collapse with<br />
an uncontrolled inflow of brine. There-fore, a suitable decommissioning concept is currently in development.<br />
Brine inflow is managed under solution management. Uncontrolled brine inflow, however, occurs when there is a higher inflow<br />
of solution, that beyond the capability of solution management. In this case, radionuclides from radioactive wastes come into contact<br />
with brine and are dissolved into the solution. If the mine collapses, the brine is pressed into groundwater. The radionuclides<br />
could then migrate with groundwater into the biosphere and cause radioactive exposure.<br />
8) COST BENEFIT ASSESSMENT ACCORDING TO FRENCH METHODOLOGY (w/oP-59310)<br />
Philippe Pouget-Abadie, Pricop-Bass Tudor, URS (France)<br />
The site has been operated since 1903 for various metallurgy-related activities, as well as foundry activities. It covers a total<br />
surface area of 11 ha. Following the partial cessation of industrial activities, the sites western part (approximately 5 ha) was sold<br />
to a developer for the creation of an artisanal, tertiary and industrial activity estate.<br />
URS was jointly commissioned by the sites former operator and by the developer to perform complementary site characterisation<br />
studies in order to assess the sites compatibility with the future site use as well as to assess the costs of potential remedial<br />
works.<br />
131
Session 60 Abstracts<br />
A cost-benefit assessment was conducted by URS and focused on management of soils excavated in the context of the development<br />
project. The solutions considered comprised:Disposal of excavated soils in Class II or Class I landfills. This solution is the<br />
most systematic and therefore the fastest, which is an advantage in the context of the implementation of the development. However,<br />
associated costs are estimated at 2.3 M¬ and will have to be managed based on unit prices. Reuse of excavated soils on site as<br />
fill materials, combined with off-site disposal of excess non-reusable volumes. The projects grades were adjusted on this…<br />
SESSION 60 — BEST POSTERS OF ICEM 2011<br />
ABSTRACTS NOT REQUIRED<br />
NOTES<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
________________________________________________________________________________________________________<br />
132
ICEM'11 Pre-Registration Attendee List — By Last Name<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
A<br />
Dzhamshed Abdushukurov S.U.UMAROV PHYSICAL -<br />
TECHNICAL INSTITUTE OF<br />
ACADEMY OF SCIENCES OF<br />
REPUBLIC OF TAJIKISTAN<br />
Tajikistan<br />
Andris Abramenkovs LATVIAN ENVIRONMENT,<br />
GEOLOGY AND<br />
METEOROLOGY CENTRE<br />
Latvia<br />
William Abramson LAWRENCE LIVERMORE<br />
NATIONAL LABORATORY<br />
United States<br />
Rateb (Boby) Abu-Eid U.S. NRC United States<br />
Valerie Adsley GUEST United Kingdom<br />
Ian Adsley NUVIA LTD United Kingdom<br />
Joerg Aign WESTINGHOUSE ELECTRIC Germany<br />
GERMANY GMBH<br />
Fouad Al-Musawi IRAQ MINISTRY<br />
OF SCIENCEAND<br />
TECHNOLOGY<br />
Iraq<br />
Keith Anderson ECC United States<br />
Johan Andersson JA STREAMFLOW AB Sweden<br />
Thierry Andre ONET TECHNOLOGIES<br />
GRANDS PROJETS<br />
France<br />
Andrea Antus PAKS NUCLEAR POWER<br />
PLANT LTD<br />
Hungary<br />
Shiho Asai JAPAN ATOMIC ENERGY<br />
AGENCY<br />
Japan<br />
Rosemarie Atabek CEA SACLAY France<br />
Julien Attiogbe GEOVARIANCES France<br />
Emilie Aubonnet GEOVARIANCES France<br />
Annabelle Axinn<br />
B<br />
GUEST Unites States<br />
Douglas Bablitch AMEC EARTH AND<br />
INRASTRUCTURE<br />
United States<br />
Ian Bainbridge ATOMIC ENERGY OF<br />
CANADA LIMITED<br />
Canada<br />
Andrew Baker EDEN NUCLEAR AND<br />
ENVIRONMENT LTD.<br />
United Kingdom<br />
Jonathan Baker CH2M HILL United Kingdom<br />
Francesco Basile EUROPEAN COMMISSION<br />
- JRC ISPRA<br />
Italy<br />
Tamara Baldwin GALSON SCIENCES<br />
LIMITED<br />
United Kingdom<br />
Gheorghe Barariu RAAN-SITON Romania<br />
Yves Barré CEA France<br />
Angela Bartlett RESEARCH SITES<br />
RESTORATION LTD<br />
United Kingdom<br />
Olga Batyukhnova GUEST Ukraine<br />
Ian Beadle AMEC United States<br />
Christophe Behar CEA France<br />
Stephane Belbeze ANTEA France<br />
Gary Benda ICEM'11 CONFERENCE<br />
MANAGER<br />
United States<br />
Dianne Benda ICEM'11 GUEST TOURS United States<br />
Michel Berte AREVA France<br />
Claude Besson CARBODIAM S.A. Belgium<br />
Hervé Bienvenu ANDRA France<br />
Christophe Binet AREVA France<br />
Yvon Bladier CONSULTANT France<br />
Ludovic Blanc SARP INDUSTRIES France<br />
Tiffany Blanchard USDOE / NATIONAL<br />
NUCLEAR<br />
United States<br />
James Blankenhorn PERMAFIX<br />
ENVIRONMENTAL<br />
SERVICES INC<br />
United States<br />
Mikhail Bogod JSC ECOMET-S Russia<br />
Wilhelm Bollingerfehr DBE TECHNOLOGY GmbH Germany<br />
Jean-Michel Boniface AREVA TA France<br />
Robert Bonner URS United Kingdom<br />
Peter Booth WSP E&E United Kingdom<br />
Jorge Borque ENRESA Spain<br />
Jean-Michel Bosgiraud ANDRA France<br />
María Cecilia Bossio NUCLEAR REGULATORY<br />
AUTHORITY<br />
Argentina<br />
Joseph Boucau WESTINGHOUSE ELECTRIC United States<br />
COMPANY<br />
Laurel Boucher THE LAUREL CO. United States<br />
Bernard Boullis CEA-SACLAY France<br />
Jos Boussu TECNUBEL Belgium<br />
Shari Brabham CISS CORPORATION United States<br />
Pam Bradford CISS CORPORATION Unites States<br />
Marnix Braeckeveldt ONDRAF/NIRAS Belgium<br />
Georg Braehler NUKEM TECHNOLOGIES<br />
GMBH<br />
Germany<br />
Peter Brennecke CONSULTANT Germany<br />
Daniel Brew ANSTO Australia<br />
Kimberly Brewer ARS INTERNATIONAL, INC. Unites States<br />
Steven Brown SENES CONSULTANTS LTD United States<br />
Kathryn Brown GUEST United States<br />
Jerome Brueziere AREVA NC France<br />
Guy Brunel CEA France<br />
Peter Burgess NUVIA LTD United Kingdom<br />
Nazirzhon Buriev S.U.UMAROV PHYSICAL -<br />
TECHNICAL INSTITUTE OF<br />
ACADEMY OF SCIENCES OF<br />
REPUBLIC OF TAJIKISTAN<br />
Tajikistan<br />
Klaus Büttner<br />
C<br />
NUKEM<br />
TECHNOLOGIES GMBH<br />
Germany<br />
Maria Teresa Cafaggi GUEST Belgium<br />
Bruno Cahen ANDRA France<br />
Olivier Calixte ONET TECHNOLOGIES - France<br />
ONECTRA France<br />
Lionel Campayo CEA France<br />
Dwight Campbell CONTAINER PRODUCTS<br />
CORPORATION<br />
Unites States<br />
Jan Carlsson SKB Sweden<br />
Andy Carr CALDER GROUP United Kingdom<br />
Iain Carvel RESEARCH SITES<br />
RESTOTATION LTD.<br />
United Kingdom<br />
Mike Cashin PORVAIR FILTRATION<br />
GROUP LTD<br />
United Kingdom<br />
Jeremy Causse CEA France<br />
Charlotte Cazala IRSN France<br />
Didier Cerat CEA - CENTRE DE<br />
MARCOULE<br />
France<br />
Michiel Ceulemans UMICORE Belgium<br />
Jean-Michel Chabeuf AREVA France<br />
Pascal Champ CEGELEC France<br />
Neil Chapman ARIUS ASSOCIATES United States<br />
Mrs. Chapman GUEST Unites States<br />
Yih Ping Chen INSTITUTE OF NUCLEAR<br />
ENERGY RESEARCH (INER)<br />
Taiwan<br />
Sylvain Chevassu ONET TECHNOLOGIES -<br />
ONECTRA<br />
France<br />
Jean-Paul Chiles ECOLE DES MINES DE<br />
PARIS<br />
France<br />
Apostolos Christodoulou VJ TECHNOLOGIES France<br />
Robert Clark NUVIA LIMITED United Kingdom<br />
Jane Clarke GUEST Canada<br />
Gilles Clement AREVA BUVAL United States<br />
Jean Pierre Cizel AREVA United States<br />
John Cochran SANDIA NATIONAL<br />
LABORATORIES<br />
United States<br />
Hans Codée COVRA N.V. Netherlands<br />
Matthew Cole SA TECHNOLOGY United States<br />
Danny Coleman ARS INTERNATIONAL, INC. Unites States<br />
Yvette Collazo U.S. DEPARTMENT OF<br />
ENERGY<br />
Unites States<br />
Judith Connell FLUOR United States<br />
Carl Connell GUEST Unites States<br />
Kevin Cook CERADYNE BORON<br />
PRODUCTS<br />
United States<br />
133
134<br />
ICEM'11 Pre-Registration Attendee List — By Last Name<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
Michael Cournoyer LOS ALAMOS NATIONAL<br />
LABORATORY<br />
United States<br />
Jean-Marie Cuchet BELGONUCLEAIRE Belgium<br />
Michael Cull TELEDYNE BROWN<br />
ENGINEERING<br />
United States<br />
Dan Curry<br />
D<br />
URS United Kingdom<br />
Erik Dagorn BUREAU VERITAS France<br />
Vladimir Daniska DECOM, A.S. Slovak Republic<br />
Didier Dall'ava CEA SACLAY France<br />
Frederique Damerval AREVA France<br />
Géraldine Dandrieux ASN France<br />
Carol Darbyshire SPRINGFIELDS FUELS LTD United Kingdom<br />
Mike Davies NUVIA LIMITED United Kingdom<br />
Chantal De Fouquet ECOLE DES MINES DE<br />
PARIS<br />
France<br />
Grégoire De Laval AREVA France<br />
Pierre-Edouard<br />
De La Ronciere<br />
SPIE France<br />
Patrick De Moura CEA France<br />
Renate De Vos NUCLEAR RESEARCH<br />
AND CONSULTANCY<br />
GROUP<br />
Netherlands<br />
Fabian De Weirdt GEOPROBE<br />
ENVIROMENTAL<br />
TECHNOLOGIES S.A.<br />
Belgium<br />
Frank Deconinck CNE France<br />
Ronald Dekker NRG Netherlands<br />
Bernard Delannay CARBODIAM S.A. Belgium<br />
Sylvie Delaplace SFEN France<br />
Carole Delchet INSTITUT DE CHIMIE<br />
SÉPARATIVE DE<br />
MARCOULE, UMR 5257<br />
France<br />
Anne Delos AMPHOS 21<br />
CONSULTING SL<br />
France<br />
Andrea Denby ATOMIC ENERGY OF<br />
CANADA LIMITED<br />
Canada<br />
Mark Denton KURION, INC. United States<br />
Debbie Denton GUEST Unites States<br />
Yvon Desnoyers GEOVARIANCES France<br />
Jas Devgun SARGENT & LUNDY United States<br />
Michel Dilles AMTEK SAS Unites States<br />
Vince Dilworth ASME United States<br />
Nick DiMascio BARTLETT SERVICES INC. United States<br />
Paul Dixon LOS ALAMOS NATIONAL<br />
LABORATORY<br />
United States<br />
Mrs. Dixon Dixon GUEST Unites States<br />
Ryosuke Doke JAPAN ATOMIC<br />
ENERGY AGENCY<br />
Japan<br />
Emma Dorado Lopez ONDRAF/NIRAS Belgium<br />
Philippe Doumerc AREVA NC France<br />
Andrew Drom ENERGYSOLUTIONS<br />
EU LTD<br />
United States<br />
James Droppo PACIFIC NORTHWEST<br />
NATIONAL LABORATORY<br />
United States<br />
Tamar Droppo GUEST Unites States<br />
Didier Dubot CEA France<br />
Géraldine Dupuy DEWDROPS France<br />
Felicia Durán SANDIA NATIONAL<br />
LABORATORIES<br />
United States<br />
Anne Durand CEA CENTRE DE<br />
MARCOULE<br />
France<br />
Michel Dutzer<br />
E<br />
ANDRA France<br />
Takeshi Ebashi NUCLEAR WASTE<br />
MANAGEMENT<br />
ORGANIZATION OF<br />
JAPAN (NUMO)<br />
Japan<br />
Andrew Edwards GUEST Unites States<br />
Henrik Efraimsson SWEDISH RADIATION<br />
SAFETY AUTHORITY<br />
Sweden<br />
Fredrik Ekenborg AB SVAFO Sweden<br />
Enik Elter PAKS NUCLEAR<br />
POWER PLANT LTD<br />
Hungary<br />
William Everett<br />
F<br />
DEWDROPS France<br />
Sebastien Farin ANDRA France<br />
Kapila Fernando AUSTRALIAN NUCLEAR<br />
SCIENCE AND<br />
TECHNOLOGY<br />
ORGANISATION<br />
Australia<br />
Enoka Fernando GUEST Australia<br />
Christopher Fisher OFFICE OF NUCLEAR<br />
REGULATION<br />
United Kingdom<br />
Amelia Fogleman GUEST Unites States<br />
Dyan Foss CH2M HILL PLATEAU<br />
REMEDIATION COMPANY<br />
United States<br />
Adam Foster STUDSVIK, INC. United States<br />
Angelika Fox CWN GRUPPE<br />
BARSBÜTTEL<br />
Germany<br />
Dominique AGORATEK Canada<br />
Francois-Bongarcon INTERNATIONAL<br />
Laszlo Fritz<br />
G<br />
PUBLIC LIMITED<br />
COMPANY FOR<br />
RADIOACTIVE WASTE<br />
MANAGEMENT (PURAM)<br />
Hungary<br />
Miklos Garamszeghy NWMO Canada<br />
Ester García Tapias ENRESA Spain<br />
Irina Gaus NAGRA Switzerland<br />
Arnaud Gay AREVA France<br />
Robert Geddes AMEC Canada<br />
Alexander Gelbutovskiy JSC ECOMET-S Russia<br />
Mark Gerchikov AMEC NSS Canada<br />
Ludivine Gilli IRSN France<br />
Emmanuel Girasa GDF SUEZ NUCLÉAIRE<br />
FRANCE<br />
France<br />
Patrick Gobert WESTINGHOUSE<br />
ELECTRIC COMPANY<br />
United States<br />
Rebecca Goddard GUEST Unites States<br />
François-Michel Gonnot ANDRA France<br />
Alexandre Gorbatchev COMMISSARIAT A<br />
L'ENERGIE ATOMIQUE<br />
ET AUX ENERGIES<br />
ALTERNATIVES<br />
France<br />
Florence Goutelard CEA United States<br />
Kapil Goyal LOS ALAMOS NATIONAL<br />
LABORATORY<br />
United States<br />
Achla Goyal GUEST Unites States<br />
Agnes Grandjean CEA France<br />
Guy Granier CEA MARCOULE France<br />
Dominique Grenêche SFEN France<br />
Christian Gronemeyer GRS MBH Germany<br />
Philippe Gros-Gean ONET TECHNOLOGIES France<br />
Bertil Grundfelt KEMAKTA KONSULT AB Sweden<br />
Philippe Guetat CEA France<br />
Philippe Guiberteau<br />
H<br />
CEA SACLAY France<br />
Steve Halliwell VJ TECHNOLOGIES, INC. United States<br />
Matthieu Hallouin ANTEA GROUP France<br />
Patricia Hamel-Bloch SFEN France<br />
Eduard Hanslík T.G.MASARYK WATER<br />
RESEARCH INSTITUTE<br />
Czech Republic<br />
Vaclav Hanusik VUJE, Inc. Slovak Republic<br />
Tomoko Haraga JAPAN ATOMIC ENERGY<br />
AGENCY<br />
Japan<br />
Frank Hardeman SCK-CEN Belgium<br />
Susetyo Hario Putero GADJAH MADA<br />
UNIVERSITY<br />
Indonesia<br />
Lee Hartley SERCO United Kingdom<br />
Haruhi Hata JAPAN ATOMIC ENERGY<br />
AGENCY<br />
Japan<br />
Markus Havertz FORSCHUNGZENTRUM<br />
JÜLICH GMBH<br />
Germany<br />
Susan Hess AREVA United States<br />
Alan Heyes KING'S COLLEGE, LONDON United Kingdom
ICEM'11 Pre-Registration Attendee List — By Last Name<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
Cathy Hickey CH2M HILL United States<br />
Tim Hicks GALSON SCIENCES<br />
LIMITED<br />
United Kingdom<br />
Günter Hillebrand NUCLEAR ENGINEERING<br />
SEIBERSDORF GMBH<br />
Austria<br />
John Hollinden CONTAINER PRODUCTS<br />
CORPORATION<br />
Unites States<br />
Dae-Seok Hong KAERI (KOREA ATOMIC<br />
ENERGY RESEARCH<br />
INSTITUTE)<br />
Korea<br />
Koch Horst RÖHR+STOLBERG GMBH Germany<br />
Tomas Hrncir SLOVAK UNIVERSITY OF<br />
TECHNOLOGY IN<br />
BRATISLAVA<br />
Slovak Republic<br />
Karl Hughes BABCOCK<br />
INTERNATIONAL<br />
United Kingdom<br />
Tim Hunter THE UNIVERSITY<br />
OF LEEDS<br />
United Kingdom<br />
Arne Hüttmann<br />
I<br />
UMICORE Belgium<br />
Atsushi Iizuka KOBE UNIVERSITY Japan<br />
Nathalie Impens SCK-CEN Belgium<br />
Tomoko Ishii RADIOACTIVE WASTE<br />
MANAGEMENT FUNDING<br />
AND RESEARCH CENTER<br />
Japan<br />
Tomohiro Ito OSAKA PREFECTURE<br />
UNIVERSITY<br />
Japan<br />
Oleg Ivanov<br />
J<br />
NRC KURCHATOV<br />
INSTITUTE<br />
Russia<br />
Albert Jacobs DEWDROPS France<br />
Michael James SELLAFIELD LTD United Kingdom<br />
David James DW JAMES<br />
CONSULTING, LLC<br />
United States<br />
Juanita James GUEST Unites States<br />
Steven Jameson STUDSVIK United States<br />
Danielle Jansik PACIFIC NORTHWEST<br />
NATIONAL LABORARY<br />
United States<br />
Michel Jeanjacques CEA/DEN/MAR/DPAD/CPRP France<br />
Nicolas Jeannee GEOVARIANCES France<br />
Chun-Ping Jen DEPT. MECHNICAL<br />
ENGINEERING, NATIONAL<br />
CHUNG CHENG<br />
UNIVERSITY<br />
Taiwan<br />
Jongseon Jeon ENESYS CO., LTD. Korea<br />
Bernard Jolly SFEN France<br />
Angie Jones AMEC United States<br />
Sammy Jones GUEST Unites States<br />
Steven Joyce SERCO United Kingdom<br />
Lawrence Judd NUVISION ENGINEERING United States<br />
László Juhász NATIONAL RESEARCH<br />
INSTITUTE FOR<br />
RADIOBIOLOGY AND<br />
RADIOHYGIENE<br />
Hungary<br />
Hagen Gunther Jung<br />
K<br />
NLWKN Germany<br />
Dawn Kaback AMEC GEOMATRIX United States<br />
Dennis Kelley PACIFI NUCLEAR<br />
SOLUTIONS<br />
United States<br />
Terry Kelly PAR SYSTEMS LTD United Kingdom<br />
Jeffrey Kerridge CH2M HILL United States<br />
Ronald Keyser ORTEC United States<br />
Merry Keyser GUEST Unites States<br />
Kwang-Wook Kim KOREA ATOMIC ENERGY<br />
RESEARCH INSTITUTE<br />
Korea<br />
Karen Kim ELECTRIC POWER<br />
RESEARCH INSTITUTE<br />
United States<br />
Kazumi Kitayama NUCLEAR WASTE<br />
MANAGEMENT<br />
ORGANIZATION OF<br />
JAPAN (NUMO)<br />
Japan<br />
Heather Klebba NFT United States<br />
Thomas Kluth SIEMPELKAMP<br />
NUK+LEARTECHNIK<br />
GMBH<br />
Germany<br />
Kelly Knight BECHTEL NATIONAL, INC. United States<br />
Ichizo Kobayashi KAJIMA CORPORATION Japan<br />
Frank Köhler RÖHR + STOLBERG GMBH Germany<br />
Ken Kok ASME United States<br />
Ville Koskinen FORTUM Finland<br />
Paul Kreitman WESTINGHOUSE<br />
NUCLEAR SERVICES<br />
United States<br />
Heinz Kröger TÜV NORD ENSYS<br />
HANNOVER GMBH<br />
& CO. KG<br />
Germany<br />
Albert Kruger US DOE United States<br />
Konstantin Kulikov NIPTB ONEGA OAO Russia<br />
Takanori Kunimaru<br />
L<br />
JAEA Japan<br />
Jean Paul Labeur AREVA - DAP France<br />
Alastair Laird PROJECT TIME & COST United Kingdom<br />
Tai-Wei Lan FUEL CYCLE AND<br />
MATERIAL<br />
ADMINISTRATION ATOMIC<br />
ENERGY COUNCIL<br />
Taiwan<br />
Patrick Landais ANDRA France<br />
Eric Lanes ANDRA France<br />
Barbara Larsen GUEST Unites States<br />
Toro Laszlo MATEFIN BUCURESTI Romania<br />
Agnes Launay AREVA France<br />
Gerard Laurent EDF/CIDEN United States<br />
Marie Lavielle CEA France<br />
Michèle Le Goff SFEN France<br />
Arnaud Leclaire ANDRA France<br />
Stephen Leclere SELLAFIELD LIMITED United Kingdom<br />
John Lehew CH2M HILL PLATEAU<br />
REMEDIATION COMPANY<br />
United States<br />
Alain Lemmens GDF SUEZ Belgium<br />
Koen Lenie TECNUBEL Belgium<br />
Célia Lepeytre CEA France<br />
Bertrand Leterme SCK-CEN Belgium<br />
Maria Lindberg STUDSVIK NUCLEAR AB Sweden<br />
Pierre Lisbonne CEA France<br />
Yung Liu ARGONNE NATIONAL<br />
LABORATORY<br />
United States<br />
Jeffrey Lively<br />
M<br />
AMEC United States<br />
Angela Mackintosh SELLAFIELD LIMITED United Kingdom<br />
Juliann Maffett EDGEN MURRAY United States<br />
Ryan Maitland OFFICE FOR NUCLEAR<br />
REGULATION<br />
United Kingdom<br />
Tatiana Makarchuk JSC ATOMSTROYEXPORT Russia<br />
Annafrancesca Mariani SOGIN S.P.A. Italy<br />
Simon Martin SELLAFIELD LTD United Kingdom<br />
Laurent Martinet AREVA NC France<br />
John Mathieson NUCLEAR<br />
DECOMMISSIONING<br />
AUTHORITY<br />
United Kingdom<br />
Mrs. McCombie GUEST Switzerland<br />
Charles McCombie ARIUS ASSOCIATION Switzerland<br />
Keith McConnell U.S. NUCLEAR<br />
REGULATORY<br />
COMMISSION<br />
United States<br />
Jan Medved VUJE, INC. Slovak Republic<br />
Afat Mehdiyeva NATIONAL AEROSPACE<br />
AGENCY OF AZERBAIJAN<br />
Azerbaijan Republic<br />
Irena Mele IAEA Austria<br />
Aurélie Merceille CEA MARCOULE France<br />
Matthias Messer GNS Germany<br />
Betty Meyer GUEST United States<br />
Greg Meyer FLUOR GOVERNMENT<br />
GROUP<br />
United States<br />
Arnaud Michelle SARP INDUSTRIES France<br />
Maxime Michel-Noel ONET TECHNOLOGIES<br />
- ONECTRA<br />
France<br />
Bill Miller AMEC United Kingdom<br />
Ross Miller SANDIA NATIONAL<br />
LABORATORIES<br />
United States<br />
135
136<br />
ICEM'11 Pre-Registration Attendee List — By Last Name<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
Sergii Mitichkin CHERNOBYL NPP Ukraine<br />
Motoyuki Mitsuda JAPAN ATOMIC<br />
ENERGY AGENCY<br />
Japan<br />
Satoru Miyoshi OBAYASHI CORPORATION Japan<br />
Fabrice Moggia AREVA France<br />
Barry Moloney ENERGYSOLUTIONS United Kingdom<br />
Jenny Morris GALSON SCIENCES<br />
LIMITED<br />
United Kingdom<br />
Ronald Morris WESTINGHOUSE<br />
ELECTRIC COMPANY<br />
USA<br />
United States<br />
Mark Morton WORLEYPARSONS<br />
POLESTAR<br />
United States<br />
Virginia Morton GUEST Unites States<br />
Gary Mottershead VJ TECHNOLOGIES, INC. United States<br />
Joachim Mueth PAUL SCHERRER INSTITUT Switzerland<br />
Virgene Mulligan ARS INTERNATIONAL United States<br />
Ronnie Mulligan GUEST Unites States<br />
André Musolff BAM FEDERAL INSTITUTE Germany<br />
FOR MATERIALS<br />
RESEARCH AND TESTING<br />
Tracy Mustin U.S. DEPARTMENT OF<br />
ENERGY<br />
Unites States<br />
Gus Myers<br />
N<br />
BABCOCK SERVICES INC. United States<br />
Jalal Naghiyev INSTITUTE OF RADIATION<br />
PROBLEMS<br />
Azerbaijan Republic<br />
Takahiro Nakajima RWMC, JAPAN Japan<br />
Garik Nalbandyan AREV SI CJSC Armenia<br />
Vladimir Necas SLOVAK UNIVERSITY<br />
OF TECHNOLOGY<br />
Slovak Republic<br />
Linde Nel NECSA South Africa<br />
Thomas Nellemann DANISH<br />
DECOMMISSIONING<br />
Denmark<br />
Tino Neumeyer BAM FEDERAL<br />
INSTITUTE FOR<br />
MATERIALS RESEARCH<br />
AND TESTING<br />
Germany<br />
Mike Nichols PACTEC EPS LTD. Unites States<br />
Massimiliano Nobile PROJECT<br />
MANAGEMENT UNIT<br />
Russia<br />
Jean-Guy Nokhamzon CEA France<br />
Christian Nowak CWN GRUPPE BARSBÜTTEL Germany<br />
Bálint Nos PURAM Hungary<br />
William Nutt<br />
O<br />
ARGONNE NATIONAL<br />
LABORATORY<br />
United States<br />
Palut-Laurent Odile ASN France<br />
Rachel O'donnell LLWR United Kingdom<br />
Takao Ohi NUCLEAR WASTE<br />
MANAGEMENT<br />
ORGANIZATION OF<br />
JAPAN (NUMO)<br />
Japan<br />
Michael Ojovan UNIVERSITY OF<br />
SHEFFIELD<br />
United Kingdom<br />
Ralf Ohlhof TUEV NORD ENSYS<br />
GMBH & CO<br />
Germany<br />
Keisuke Okumura JAPAN ATOMIC ENERGY<br />
AGENCY (JAEA)<br />
Japan<br />
Donald Olson COLUMBIANA HI TECH United States<br />
Frantisek Ondra DECOM, A.S. Slovak Republic<br />
Hironori Onoe JAPAN ATOMIC<br />
ENERGY AGENCY<br />
Japan<br />
Peter Ormai INTERNATIONAL<br />
ATOMIC AGENCY (IAEA)<br />
Austria<br />
Gérald Ouzounian ANDRA France<br />
Hitoshi Owada RADIOACTIVE WASTE<br />
MANAGEMENT FUNDING<br />
AND RESEARCH CENTER<br />
Japan<br />
Eliza Ozaine WESTINGHOUSE<br />
ELECTRIC GERMANY<br />
GMBH<br />
Germany<br />
P<br />
Michal Panik SLOVAK UNIVERSITY<br />
OF TECHNOLOGY IN<br />
BRATISLAVA<br />
Slovak Republic<br />
Alexandros Papafotiou INTERA INC. SWISS<br />
BRANCH<br />
Switzerland<br />
Martial Pardoen ELECTRABEL - GDF SUEZ Belgium<br />
Alan Paulley QUINTESSA United Kingdom<br />
Maiju Paunonen FORTUM POWER &<br />
HEAT/ NUCLEAR WASTE<br />
Finland<br />
Stéphane Pepin FEDERAL AGENCY FOR<br />
NUCLEAR CONTROL<br />
Belgium<br />
Jean-Jacques Peraudin GEOVARIANCES United States<br />
Janez Perko BELGIAN NUCLEAR<br />
RESEARCH CENTRE<br />
SCK-CEN<br />
Belgium<br />
Geoffrey Peter OREGON INSTITUTE<br />
OF TECHNOLOGY<br />
PORTLAND CAMPUS<br />
United States<br />
Lucien Pillette-Cousin AREVA TA France<br />
Patrick Pin AREVA NC France<br />
Martin Plys FAUSKE &<br />
ASSOCIATES, LLC<br />
United States<br />
Richard Poisson ANDRA France<br />
Andreas Poller NAGRA, SWITZERLAND Switzerland<br />
Edward Posivak WMG, INC. United States<br />
Gilles Potier AREVA NC France<br />
Calvert Pratt BABCOCK<br />
NUCLEAR LIMITED<br />
France<br />
Jozef Pritrsky DECOM, A.S. Slovak Republic<br />
John Proni FLORIDA<br />
INTERNATIONAL<br />
UNIVERSITY<br />
United States<br />
Maria Elena Proni<br />
Q<br />
GUEST Unites States<br />
Thomas Quercetti BAM FEDERAL Germany<br />
INSTITUTE FOR MATERIALS<br />
RESEARCH AND TESTING<br />
R<br />
Krisztian Rado PUBLIC LIMITED COMPANY Hungary<br />
FOR RADIOACTIVE<br />
WASTE MANAGEMENT<br />
(PURAM)<br />
Rodolphe Raffard ANDRA France<br />
Rosa Ramirez U.S. DEPARTMENT<br />
OF ENERGY<br />
United States<br />
Rodrigo Raposo FEDERAL FLUMINENSE Brazil<br />
De Almeida UNIVERSITY<br />
John Raymont KURION, INC. United States<br />
Marilyn Raymont GUEST Unites States<br />
Reginald Recco AMETEK SAS Unites States<br />
Philip Rendell NDA (RADIOACTIVE<br />
WASTE MANAGEMENT<br />
DIRECTORATE)<br />
United Kingdom<br />
Ian Richardson SELLAFIELD LIMITED United Kingdom<br />
Steve Rima AMEC United States<br />
Stéphanie Romero ALSTOM GRID France<br />
Julie Rosello CEA CADARACHE France<br />
Francesco Rossi EUROPEAN COMMISSION<br />
- JRC ISPRA<br />
Italy<br />
David Rossiter LLW REPOSITORY LTD United Kingdom<br />
Bernard Rottner ONET TECHNOLOGIES Unites States<br />
Anne Marie Roux CEA France<br />
Jean-Paul Roux GEOVARIANCES France<br />
Joerg Rueedi NAGRA Switzerland<br />
James Russell NEVADA NATIONAL<br />
SECURITY SITE<br />
United States<br />
Woo-Seog Ryu<br />
S<br />
KAERI (KOREA ATOMIC<br />
ENERGY RESEARCH<br />
INSTITUTE)<br />
Korea<br />
Mike Sanchez PACTEC, INC. Unites States<br />
Juan L. Santiago ENRESA Spain<br />
Satoshi Sato INTERNATIONAL<br />
ACCESS CORPORATION<br />
Japan
ICEM'11 Pre-Registration Attendee List — By Last Name<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
Hisao Satoh MITSUBISHI MATERIALS<br />
CORPORATION<br />
Japan<br />
Lutz Schneider STOLLER<br />
INGENIEURTECHNIK GMBH<br />
Germany<br />
Jürg Schneider NAGRA, SWITZERLAND Switzerland<br />
Richard Schwent GUEST Unites States<br />
Daniela Seda GUEST Brazil<br />
Kelly Sedor NUCLEAR WASTE<br />
MANAGEMENT<br />
ORGANIZATION<br />
Canada<br />
Sergey Semenov NATIONAL RESEARCH<br />
CENTRE "KURCHATOV<br />
INSTITUTE<br />
Russia<br />
Rainer Senger INTERA INC. SWISS<br />
BRANCH<br />
Switzerland<br />
Emad Sharmsaldin IRAQ MINISTRY OF<br />
SCIENCE AND<br />
TECHNOLOGY<br />
Iraq<br />
John Shevelan LLWR LTD United Kingdom<br />
Bill Shingler FLUOR GOVERNMENT<br />
GROUP<br />
United States<br />
Peter Sibley ENERGYSOLUTIONS United Kingdom<br />
Rolf Sjöblom TEKEDO AB Sweden<br />
Alojz Slaninka VUJE, A.S. Slovak Republic<br />
Ondrej Slávik VUJE, A.S. Slovak Republic<br />
Joe Small UK NATIONAL<br />
NUCLEAR LABORATORY<br />
United Kingdom<br />
Graham Smith GMS ABINGDON LTD United Kingdom<br />
Jager Smith ENTERGY United States<br />
Janet Smith GUEST Unites States<br />
Malgorzata Sneve NRPA Norway<br />
Marina Sokcic-Kostic NUKEM TECHNOLOGIES<br />
GMBH<br />
Germany<br />
Stephanie Soton AREVA NC France<br />
Thorsten Stahl GRS MBH Germany<br />
Mathias Steinhoff ÖKO-INSTITUT Germany<br />
Hans-Juergen Steinmetz FORSCHUNGSZENTRUM<br />
JÜLICH GMBH<br />
Germany<br />
Vyacheslav Stepanov NRC KURCHATOV<br />
INSTITUTE<br />
Russia<br />
Dmitry Stepennov NATIONAL RESEARCH<br />
CENTRE "KURCHATOV<br />
INSTITUTE"<br />
Russia<br />
Howard Stevens STUDSVIK, INC. United States<br />
Dawn Stevens GUEST Unites States<br />
Trevor Sumerling LLWR LTD United Kingdom<br />
Karel Svoboda NUCLEAR RESEARCH<br />
INSTITUTE REZ PLC.<br />
Czech Republic<br />
Milena Svoboda GUEST Czech Republic<br />
Bryan Swinson PAJARITO SCIENTIFIC<br />
CORPORATION<br />
United States<br />
Susan Sykes GUEST Canada<br />
Jonathan Sykes<br />
T<br />
UNIVERSITY OF<br />
WATERLOO<br />
Canada<br />
Ulrike Tack-Hillebrand GUEST Austria<br />
Yusuke Takayama KOBE UNIVERSITY Japan<br />
Stefan Thierfeldt BRENK<br />
SYSTEMPLANUNG GMBH<br />
Germany<br />
Chauveau Thomas BOUYGUES<br />
CONSTRUCTION<br />
SERVICES NUCLEAIRES<br />
France<br />
Simon Thompson ENERGY SOLUTIONS United Kingdom<br />
Patrice Torres ANDRA France<br />
Yuki Tosaki GEOLOGICAL SURVEY<br />
OF JAPAN, AIST<br />
Japan<br />
Pierre Trabuc CEA France<br />
Ivo Tripputi SOGIN S.P.A. Italy<br />
Peter Turza PUBLIC LIMITED<br />
COMPANY FOR<br />
RADIOACTIVE WASTE<br />
MANAGEMENT (PURAM),<br />
HUNGARY<br />
Hungary<br />
Chou Tzu-Hsing<br />
U<br />
INSTITUTE OF NUCLEAR<br />
ENERGY RESEARCH<br />
Taiwan<br />
Daniele Ugolini CONSULTANT Italy<br />
Ehrlicher Ulrich PAUL SCHERRER INSTITUT Switzerland<br />
Veronika Ustohalova<br />
V<br />
OEKO-INSTITUT E.V. Germany<br />
Walter Van Hecke AREVA France<br />
Leo Van Velzen NUCLEAR RESEARCH &<br />
CONSULTANCY GROUP<br />
Netherlands<br />
Rik Vanbrabant BELGOPROCESS Belgium<br />
Tjalle Vandergraaf PROVIDENCE COLLEGE Canada<br />
Evelyn Vandergraaf GUEST Canada<br />
Serge Vanderperre TRACTEBEL ENGINEERING Belgium<br />
Thierry Varet AREVA France<br />
Tero Varjoranta INTERNATIONAL ATOMIC<br />
ENERGY AGENCY (IAEA)<br />
Austria<br />
Claire-Emilie Vaudey AREVA France<br />
Romain Vede AREVA France<br />
Andreas Vesely NUCLEAR ENGINEERING<br />
SEIBERSDORF<br />
Austria<br />
Jean-Marc Vidal COMMISSARIAT À<br />
L'ENERGIE ATOMIQUE<br />
France<br />
Joerg Viermann GNS GESELLSCHAFT FUER Germany<br />
NUKLEAR-SERVICE MBH<br />
Bernard Vigreux SFEN France<br />
Bernard Vignau<br />
W<br />
CEA SACLAY United States<br />
Charles Waggoner INSTITUTE FOR CLEAN<br />
ENERGY TECHNOLOGY<br />
United States<br />
André Wakker NRG Netherlands<br />
Julie Ward ABORIGINAL AFFAIRS<br />
AND NORTHERN<br />
DEVELOPMENT<br />
Canada<br />
Michael Washer FOREIGN AFFAIRS<br />
AND INTERNATIONAL<br />
TRADE CANADA<br />
Canada<br />
Pippa Waterman ENERGYSOLUTIONS United Kingdom<br />
Tsong-Yang Wei INSTITUTE OF NUCLEAR<br />
ENERGY RESEARCH,<br />
AEC, TAIWAN<br />
Taiwan<br />
Jeroen Welbergen COVRA N.V. United States<br />
David Wells NUVIA LIMITED United Kingdom<br />
Stephen Wickham GALSON SCIENCES LTD United Kingdom<br />
Anders Wiebert SWEDISH RADIATION<br />
SAFETY AUTHORITY Sweden<br />
Craig Williamson SOUTH CAROLINA<br />
RESEARCH AND<br />
EDUCATION<br />
FOUNDATION<br />
United States<br />
Bertrand Willmann AREVA United States<br />
Keith Witwer IMPACT SERVICES, INC.,<br />
GEOMELT DIVISION United States<br />
Hui-Jun Won KAERI Korea<br />
Christopher Woodhead<br />
Y<br />
SA ROBOTICS LTD United Kingdom<br />
Shuichi Yamamoto OBAYASHI CORPORATION Japan<br />
James Young<br />
Z<br />
UNIVERSITY OF LEEDS United Kingdom<br />
Matej Zachar DECOM, A.S. Slovak Republic<br />
André Zech SARP INDUSTRIES France<br />
Robert L. Zelmer AECL - LLRWMO Canada<br />
Donna Zelmer GUEST Canada<br />
Franco Zorzoli CAMPOVERDE SRL Italy<br />
Maria Zorzoli GUEST Italy<br />
137
138<br />
ICEM'11 Pre-Registration Attendee List — By Country<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
Armenia<br />
Garik Nalbandyan AREV SI CJSC Armenia<br />
Argentina<br />
María Cecilia Bossio<br />
Australia<br />
NUCLEAR REGULATORY<br />
AUTHORITY<br />
Argentina<br />
Daniel Brew ANSTO Australia<br />
Kapila Fernando AUSTRALIAN NUCLEAR<br />
SCIENCE AND<br />
TECHNOLOGY<br />
ORGANISATION<br />
Australia<br />
Enoka Fernando<br />
Austria<br />
GUEST Australia<br />
Günter Hillebrand NUCLEAR ENGINEERING<br />
SEIBERSDORF GMBH<br />
Austria<br />
Irena Mele IAEA Austria<br />
Peter Ormai INTERNATIONAL ATOMIC<br />
AGENCY (IAEA)<br />
Austria<br />
Ulrike Tack-Hillebrand GUEST Austria<br />
Tero Varjoranta INTERNATIONAL ATOMIC<br />
ENERGY AGENCY (IAEA)<br />
Austria<br />
Andreas Vesely<br />
Azerbaijan Republic<br />
NUCLEAR ENGINEERING<br />
SEIBERSDORF<br />
Austria<br />
Afat Mehdiyeva NATIONAL AEROSPACE<br />
AGENCY OF AZERBAIJAN<br />
Azerbaijan Republic<br />
Jalal Naghiyev<br />
Belgium<br />
INSTITUTE OF<br />
RADIATION PROBLEMS<br />
Azerbaijan Republic<br />
Claude Besson CARBODIAM S.A. Belgium<br />
Jos Boussu TECNUBEL Belgium<br />
Marnix Braeckeveldt ONDRAF/NIRAS Belgium<br />
Maria Teresa Cafaggi GUEST Belgium<br />
Michiel Ceulemans UMICORE Belgium<br />
Jean-Marie Cuchet BELGONUCLEAIRE Belgium<br />
Fabian De Weirdt GEOPROBE<br />
ENVIROMENTAL<br />
TECHNOLOGIES S.A.<br />
Belgium<br />
Bernard Delannay CARBODIAM S.A. Belgium<br />
Emma Dorado Lopez ONDRAF/NIRAS Belgium<br />
Frank Hardeman SCK-CEN Belgium<br />
Arne Hüttmann UMICORE Belgium<br />
Nathalie Impens SCK-CEN Belgium<br />
Alain Lemmens GDF SUEZ Belgium<br />
Koen Lenie TECNUBEL Belgium<br />
Bertrand Leterme SCK-CEN Belgium<br />
Martial Pardoen ELECTRABEL - GDF SUEZ Belgium<br />
Stéphane Pepin FEDERAL AGENCY FOR<br />
NUCLEAR CONTROL<br />
Belgium<br />
Janez Perko BELGIAN NUCLEAR<br />
RESEARCH CENTRE<br />
SCK-CEN<br />
Belgium<br />
Rik Vanbrabant BELGOPROCESS Belgium<br />
Serge Vanderperre<br />
Brazil<br />
TRACTEBEL ENGINEERING Belgium<br />
Rodrigo Raposo FEDERAL FLUMINENSE Brazil<br />
De Almeida UNIVERSITY<br />
Daniela Seda<br />
Canada<br />
GUEST Brazil<br />
Ian Bainbridge ATOMIC ENERGY OF<br />
CANADA LIMITED<br />
Canada<br />
Jane Clarke GUEST Canada<br />
Andrea Denby ATOMIC ENERGY OF<br />
CANADA LIMITED<br />
Canada<br />
Dominique AGORATEK Canada<br />
Francois-Bongarcon INTERNATIONAL<br />
Miklos Garamszeghy NWMO Canada<br />
Robert Geddes AMEC Canada<br />
Mark Gerchikov AMEC NSS Canada<br />
Kelly Sedor NUCLEAR WASTE<br />
MANAGEMENT<br />
ORGANIZATION<br />
Canada<br />
Susan Sykes GUEST Canada<br />
Jonathan Sykes UNIVERSITY OF<br />
WATERLOO<br />
Canada<br />
Tjalle Vandergraaf PROVIDENCE COLLEGE Canada<br />
Evelyn Vandergraaf GUEST Canada<br />
Julie Ward ABORIGINAL AFFAIRS<br />
AND NORTHERN<br />
DEVELOPMENT<br />
Canada<br />
Michael Washer FOREIGN AFFAIRS<br />
AND INTERNATIONAL<br />
TRADE CANADA<br />
Canada<br />
Robert L. Zelmer AECL - LLRWMO Canada<br />
Donna Zelmer<br />
Czech Republic<br />
GUEST Canada<br />
Eduard Hanslík T.G.MASARYK WATER<br />
RESEARCH INSTITUTE<br />
Czech Republic<br />
Karel Svoboda NUCLEAR RESEARCH<br />
INSTITUTE REZ PLC.<br />
Czech Republic<br />
Milena Svoboda<br />
Denmark<br />
GUEST Czech Republic<br />
Thomas Nellemann<br />
Finland<br />
DANISH<br />
DECOMMISSIONING<br />
Denmark<br />
Ville Koskinen FORTUM Finland<br />
Maiju Paunonen<br />
France<br />
FORTUM POWER &<br />
HEAT/ NUCLEAR WASTE<br />
Finland<br />
Thierry Andre ONET TECHNOLOGIES<br />
GRANDS PROJETS<br />
France<br />
Rosemarie Atabek CEA SACLAY France<br />
Julien Attiogbe GEOVARIANCES France<br />
Emilie Aubonnet GEOVARIANCES France<br />
Yves Barré CEA France<br />
Christophe Behar CEA France<br />
Stephane Belbeze ANTEA France<br />
Michel Berte AREVA France<br />
Hervé Bienvenu ANDRA France<br />
Christophe Binet AREVA France<br />
Yvon Bladier CONSULTANT France<br />
Ludovic Blanc SARP INDUSTRIES France<br />
Jean-Michel Boniface AREVA TA France<br />
Jean-Michel Bosgiraud ANDRA France<br />
Bernard Boullis CEA-SACLAY France<br />
Jerome Brueziere AREVA NC France<br />
Guy Brunel CEA France<br />
Bruno Cahen ANDRA France<br />
Olivier Calixte ONET TECHNOLOGIES -<br />
ONECTRA<br />
France<br />
Lionel Campayo CEA France<br />
Jeremy Causse CEA France<br />
Charlotte Cazala IRSN France<br />
Jean-Michel Chabeuf AREVA France<br />
Pascal Champ CEGELEC France<br />
Sylvain Chevassu ONET TECHNOLOGIES -<br />
ONECTRA<br />
France<br />
Jean-Paul Chiles ECOLE DES MINES<br />
DE PARIS<br />
France<br />
Apostolos Christodoulou VJ TECHNOLOGIES France<br />
Didier Cerat CEA - CENTRE DE<br />
MARCOULE<br />
France<br />
Erik Dagorn BUREAU VERITAS France<br />
Didier Dall'ava CEA SACLAY France<br />
Frederique Damerval AREVA France<br />
Géraldine Dandrieux ASN France<br />
Chantal De Fouquet ECOLE DES MINES<br />
DE PARIS<br />
France<br />
Grégoire De Laval AREVA France<br />
Pierre-Edouard<br />
De La Ronciere<br />
SPIE France<br />
Patrick De Moura CEA France<br />
Frank Deconinck CNE France<br />
Sylvie Delaplace SFEN France<br />
Carole Delchet INSTITUT DE CHIMIE<br />
SÉPARATIVE DE<br />
MARCOULE, UMR 5257<br />
France
ICEM'11 Pre-Registration Attendee List — By Country<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
Anne Delos AMPHOS 21 France<br />
CONSULTING SL<br />
Yvon Desnoyers GEOVARIANCES France<br />
Philippe Doumerc AREVA NC France<br />
Didier Dubot CEA France<br />
Géraldine Dupuy DEWDROPS France<br />
Anne Durand CEA CENTRE DE France<br />
MARCOULE<br />
Michel Dutzer ANDRA France<br />
William Everett DEWDROPS France<br />
Sebastien Farin ANDRA France<br />
Florence Gabillaud-Poillion ASN France<br />
Arnaud Gay AREVA France<br />
Ludivine Gilli IRSN France<br />
Emmanuel Girasa GDF SUEZ France<br />
NUCLÉAIRE FRANCE<br />
François-Michel Gonnot ANDRA France<br />
Alexandre Gorbatchev COMMISSARIAT A France<br />
L'ENERGIE ATOMIQUE<br />
ET AUX ENERGIES<br />
ALTERNATIVES<br />
Agnes Grandjean CEA France<br />
Guy Granier CEA MARCOULE France<br />
Dominique Grenêche SFEN France<br />
Philippe Gros-Gean ONET TECHNOLOGIES France<br />
Philippe Guetat CEA France<br />
Philippe Guiberteau CEA SACLAY France<br />
Matthieu Hallouin ANTEA GROUP France<br />
Patricia Hamel-Bloch SFEN France<br />
Albert Jacobs DEWDROPS France<br />
Michel Jeanjacques CEA/DEN/MAR/DPAD/CPRP France<br />
Nicolas Jeannee GEOVARIANCES France<br />
Bernard Jolly SFEN France<br />
Jean Paul Labeur AREVA - DAP France<br />
Patrick Landais ANDRA France<br />
Eric Lanes ANDRA France<br />
Agnes Launay AREVA France<br />
Marie Lavielle CEA France<br />
Michèle Le Goff SFEN France<br />
Arnaud Leclaire ANDRA France<br />
Célia Lepeytre CEA France<br />
Pierre Lisbonne CEA France<br />
Laurent Martinet AREVA NC France<br />
Aurélie Merceille CEA MARCOULE France<br />
Arnaud Michelle SARP INDUSTRIES France<br />
Maxime Michel-Noel ONET TECHNOLOGIES - France<br />
ONECTRA<br />
Fabrice Moggia AREVA France<br />
Jean-Guy Nokhamzon CEA France<br />
Palut-Laurent Odile ASN France<br />
Gérald Ouzounian ANDRA France<br />
Lucien Pillette-Cousin AREVA TA France<br />
Patrick Pin AREVA NC France<br />
Richard Poisson ANDRA France<br />
Gilles Potier AREVA NC France<br />
Calvert Pratt BABCOCK NUCLEAR France<br />
LIMITED<br />
Rodolphe Raffard ANDRA France<br />
Stéphanie Romero ALSTOM GRID France<br />
Julie Rosello CEA CADARACHE France<br />
Anne Marie Roux CEA France<br />
Jean-Paul Roux GEOVARIANCES France<br />
Stephanie Soton AREVA NC France<br />
Chauveau Thomas BOUYGUES France<br />
CONSTRUCTION<br />
SERVICES NUCLEAIRES<br />
Patrice Torres ANDRA France<br />
Pierre Trabuc CEA France<br />
Walter Van Hecke AREVA France<br />
Thierry Varet AREVA France<br />
Claire-Emilie Vaudey AREVA France<br />
Romain Vede AREVA France<br />
Jean-Marc Vidal COMMISSARIAT À France<br />
L'ENERGIE ATOMIQUE<br />
Bernard Vigreux SFEN France<br />
André Zech SARP INDUSTRIES France<br />
Germany<br />
Joerg Aign WESTINGHOUSE<br />
ELECTRIC GERMANY<br />
GMBH<br />
Germany<br />
Wilhelm Bollingerfehr DBE TECHNOLOGY GmbH Germany<br />
Georg Braehler NUKEM TECHNOLOGIES<br />
GMBH<br />
Germany<br />
Peter Brennecke CONSULTANT Germany<br />
Klaus Büttner NUKEM TECHNOLOGIES<br />
GMBH<br />
Germany<br />
Angelika Fox CWN GRUPPE<br />
BARSBÜTTEL<br />
Germany<br />
Christian Gronemeyer GRS MBH Germany<br />
Markus Havertz FORSCHUNGZENTRUM<br />
JÜLICH GMBH<br />
Germany<br />
Koch Horst RÖHR+STOLBERG GMBH Germany<br />
Hagen Gunther Jung NLWKN Germany<br />
Thomas Kluth SIEMPELKAMP<br />
NUK+LEARTECHNIK<br />
GMBH<br />
Germany<br />
Frank Köhler RÖHR + STOLBERG GMBH Germany<br />
Heinz Kröger TÜV NORD ENSYS<br />
HANNOVER GMBH<br />
& CO. KG<br />
Germany<br />
Matthias Messer GNS Germany<br />
André Musolff BAM FEDERAL INSTITUTE Germany<br />
FOR MATERIALS<br />
RESEARCH AND TESTING<br />
Tino Neumeyer BAM FEDERAL INSTITUTE Germany<br />
FOR MATERIALS<br />
RESEARCH AND TESTING<br />
Christian Nowak CWN GRUPPE BARSBÜTTEL Germany<br />
Ralf Ohlhof TUEV NORD ENSYS<br />
GMBH & CO<br />
Germany<br />
Eliza Ozaine WESTINGHOUSE ELECTRIC Germany<br />
GERMANY GMBH<br />
Thomas Quercetti BAM FEDERAL INSTITUTE Germany<br />
FOR MATERIALS<br />
RESEARCH AND TESTING<br />
Lutz Schneider STOLLER<br />
INGENIEURTECHNIK<br />
GMBH<br />
Germany<br />
Marina Sokcic-Kostic NUKEM<br />
TECHNOLOGIES GMBH\<br />
Germany<br />
Thorsten Stahl GRS MBH Germany<br />
Mathias Steinhoff ÖKO-INSTITUT Germany<br />
Hans-Juergen Steinmetz FORSCHUNGSZENTRUM<br />
JÜLICH GMBH<br />
Germany<br />
Stefan Thierfeldt BRENK<br />
SYSTEMPLANUNG GMBH\<br />
Germany<br />
Veronika Ustohalova OEKO-INSTITUT E.V. Germany<br />
Joerg Viermann<br />
Hungary<br />
GNS GESELLSCHAFT FUER Germany<br />
NUKLEAR-SERVICE MBH\<br />
Andrea Antus PAKS NUCLEAR POWER<br />
PLANT LTD<br />
Hungary<br />
Enik Elter PAKS NUCLEAR POWER<br />
PLANT LTD<br />
Hungary<br />
Laszlo Fritz PUBLIC LIMITED<br />
COMPANY FOR<br />
RADIOACTIVE WASTE<br />
MANAGEMENT (PURAM)<br />
Hungary<br />
László Juhász NATIONAL RESEARCH<br />
INSTITUTE FOR<br />
RADIOBIOLOGY AND<br />
RADIOHYGIENE\<br />
Hungary<br />
Bálint Nos PURAM Hungary<br />
Krisztian Rado PUBLIC LIMITED<br />
COMPANY FOR<br />
RADIOACTIVE WASTE<br />
MANAGEMENT (PURAM)<br />
Hungary<br />
Peter Turza<br />
Indonesia<br />
PUBLIC LIMITED<br />
COMPANY FOR<br />
RADIOACTIVE WASTE<br />
MANAGEMENT (PURAM),<br />
HUNGARY<br />
Hungary<br />
Susetyo Hario Putero GADJAH MADA<br />
UNIVERSITY<br />
Indonesia<br />
139
140<br />
ICEM'11 Pre-Registration Attendee List — By Country<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
Iraq<br />
Fouad Al-Musawi IRAQ MINISTRY OF<br />
SCIENCE AND<br />
TECHNOLOGY<br />
Iraq<br />
Emad Sharmsaldin<br />
Italy<br />
IRAQ MINISTRY OF<br />
SCIENCE AND<br />
TECHNOLOGY<br />
Iraq<br />
Francesco Basile EUROPEAN COMMISSION<br />
- JRC ISPRA<br />
Italy<br />
Annafrancesca Mariani SOGIN S.P.A. Italy<br />
Francesco Rossi EUROPEAN COMMISSION<br />
- JRC ISPRA<br />
Italy<br />
Ivo Tripputi SOGIN S.P.A. Italy<br />
Daniele Ugolini CONSULTANT Italy<br />
Franco Zorzoli CAMPOVERDE SRL Italy<br />
Maria Zorzoli<br />
Japan<br />
GUEST Italy<br />
Shiho Asai JAPAN ATOMIC<br />
ENERGY AGENCY<br />
Japan<br />
Ryosuke Doke JAPAN ATOMIC<br />
ENERGY AGENCY<br />
Japan<br />
Takeshi Ebashi NUCLEAR WASTE<br />
MANAGEMENT<br />
ORGANIZATION OF<br />
JAPAN (NUMO)<br />
Japan<br />
Tomoko Haraga JAPAN ATOMIC<br />
ENERGY AGENCY<br />
Japan<br />
Haruhi Hata JAPAN ATOMIC<br />
ENERGY AGENCY<br />
Japan<br />
Atsushi Iizuka KOBE UNIVERSITY Japan<br />
Tomoko Ishii RADIOACTIVE WASTE<br />
MANAGEMENT FUNDING<br />
AND RESEARCH CENTER<br />
Japan<br />
Tomohiro Ito OSAKA PREFECTURE<br />
UNIVERSITY<br />
Japan<br />
Kazumi Kitayama NUCLEAR WASTE<br />
MANAGEMENT<br />
ORGANIZATION OF<br />
JAPAN (NUMO)<br />
Japan<br />
Ichizo Kobayashi KAJIMA CORPORATION Japan<br />
Takanori Kunimaru JAEA Japan<br />
Motoyuki Mitsuda JAPAN ATOMIC<br />
ENERGY AGENCY<br />
Japan<br />
Satoru Miyoshi OBAYASHI CORPORATION Japan<br />
Takahiro Nakajima RWMC, JAPAN Japan<br />
Takao Ohi NUCLEAR WASTE<br />
MANAGEMENT<br />
ORGANIZATION OF<br />
JAPAN (NUMO)<br />
Japan<br />
Keisuke Okumura JAPAN ATOMIC<br />
ENERGY AGENCY (JAEA)<br />
Japan<br />
Hironori Onoe JAPAN ATOMIC<br />
ENERGY AGENCY (JAEA)<br />
Japan<br />
Hitoshi Owada RADIOACTIVE WASTE<br />
MANAGEMENT FUNDING<br />
AND RESEARCH CENTER<br />
Japan<br />
Satoshi Sato INTERNATIONAL ACCESS<br />
CORPORATION<br />
Japan<br />
Hisao Satoh MITSUBISHI MATERIALS<br />
CORPORATION<br />
Japan<br />
Yusuke Takayama KOBE UNIVERSITY Japan<br />
Yuki Tosaki GEOLOGICAL SURVEY<br />
OF JAPAN, AIST<br />
Japan<br />
Shuichi Yamamoto<br />
Korea<br />
OBAYASHI CORPORATION Japan<br />
Dae-Seok Hong KAERI (KOREA ATOMIC<br />
ENERGY RESEARCH<br />
INSTITUTE)<br />
Korea<br />
Jongseon Jeon ENESYS CO., LTD. Korea<br />
Kwang-Wook Kim KOREA ATOMIC ENERGY<br />
RESEARCH INSTITUTE<br />
Korea<br />
Woo-Seog Ryu KAERI (KOREA ATOMIC<br />
ENERGY RESEARCH<br />
INSTITUTE)<br />
Korea<br />
Hui-Jun Won KAERI Korea<br />
Latvia<br />
Andris Abramenkovs<br />
Netherlands<br />
LATVIAN ENVIRONMENT,<br />
GEOLOGY AND<br />
METEOROLOGY CENTRE<br />
Latvia<br />
Hans Codée COVRA N.V. Netherlands<br />
Renate De Vos NUCLEAR RESEARCH &<br />
CONSULTANCY GROUP<br />
Netherlands<br />
Ronald Dekker NRG Netherlands<br />
Leo Van Velzen NUCLEAR RESEARCH &<br />
CONSULTANCY GROUP<br />
Netherlands<br />
André Wakker<br />
Norway<br />
NRG Netherlands<br />
Malgorzata Sneve<br />
Romania<br />
NRPA Norway<br />
Gheorghe Barariu RAAN-SITON Romania<br />
Toro Laszlo<br />
Russia<br />
MATEFIN BUCURESTI Romania<br />
Mikhail Bogod JSC ECOMET-S Russia<br />
Alexander Gelbutovskiy JSC ECOMET-S Russia<br />
Oleg Ivanov NRC KURCHATOV<br />
INSTITUTE<br />
Russia<br />
Konstantin Kulikov NIPTB ONEGA OAO Russia<br />
Massimiliano Nobile PROJECT MANAGEMENT<br />
UNIT<br />
Russia<br />
Tatiana Makarchuk JSC ATOMSTROYEXPORT Russia<br />
Sergey Semenov NATIONAL RESEARCH<br />
CENTRE "KURCHATOV<br />
INSTITUTE<br />
Russia<br />
Vyacheslav Stepanov NRC KURCHATOV<br />
INSTITUTE<br />
Russia<br />
Dmitry Stepennov<br />
Slovak Republic<br />
NATIONAL RESEARCH<br />
CENTRE "KURCHATOV<br />
INSTITUTE"<br />
Russia<br />
Vladimir Daniska DECOM, A.S. Slovak Republic<br />
Vaclav Hanusik VUJE, Inc. Slovak Republic<br />
Tomas Hrncir SLOVAK UNIVERSITY<br />
OF TECHNOLOGY IN<br />
BRATISLAVA<br />
Slovak Republic<br />
Jan Medved VUJE, INC. Slovak Republic<br />
Vladimir Necas SLOVAK UNIVERSITY<br />
OF TECHNOLOGY<br />
Slovak Republic<br />
Frantisek Ondra DECOM, A.S. Slovak Republic<br />
Michal Panik SLOVAK UNIVERSITY<br />
OF TECHNOLOGY<br />
IN BRATISLAVA<br />
Slovak Republic<br />
Jozef Pritrsky DECOM, A.S. Slovak Republic<br />
Alojz Slaninka VUJE, A.S. Slovak Republic<br />
Ondrej Slávik VUJE, A.S. Slovak Republic<br />
Matej Zachar<br />
South Africa<br />
DECOM, A.S. Slovak Republic<br />
Linde Nel<br />
Spain<br />
NECSA South Africa<br />
Jorge Borque ENRESA Spain<br />
Juan L. Santiago ENRESA Spain<br />
Ester García Tapias<br />
Sweden<br />
ENRESA Spain<br />
Johan Andersson JA STREAMFLOW AB Sweden<br />
Jan Carlsson SKB Sweden<br />
Fredrik Ekenborg AB SVAFO Sweden<br />
Henrik Efraimsson SWEDISH RADIATION<br />
SAFETY AUTHORITY<br />
Sweden<br />
Bertil Grundfelt KEMAKTA KONSULT AB Sweden<br />
Maria Lindberg STUDSVIK NUCLEAR AB Sweden<br />
Johanna Sandwall SWEDISH RADIATION<br />
SAFETY AUTHORITY<br />
Sweden<br />
Rolf Sjöblom TEKEDO AB Sweden<br />
Anders Wiebert SWEDISH RADIATION<br />
SAFETY AUTHORITY<br />
Sweden
ICEM'11 Pre-Registration Attendee List — By Country<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
Switzerland<br />
Irina Gaus NAGRA Switzerland<br />
Mrs. McCombie GUEST Switzerland<br />
Charles McCombie ARIUS ASSOCIATION Switzerland<br />
Joachim Mueth PAUL SCHERRER<br />
INSTITUT<br />
Switzerland<br />
Alexandros Papafotiou INTERA INC.<br />
SWISS BRANCH<br />
Switzerland<br />
Andreas Poller NAGRA, SWITZERLAND Switzerland<br />
Joerg Rueedi NAGRA Switzerland<br />
Jürg Schneider NAGRA, SWITZERLAND Switzerland<br />
Rainer Senger INTERA INC. SWISS<br />
BRANCH<br />
Switzerland<br />
Ehrlicher Ulrich<br />
Taiwan<br />
PAUL SCHERRER<br />
INSTITUT<br />
Switzerland<br />
Yih Ping Chen INSTITUTE OF NUCLEAR<br />
ENERGY RESEARCH (INER)<br />
Taiwan<br />
Chun-Ping Jen DEPT. MECHNICAL<br />
ENGINEERING,<br />
NATIONAL CHUNG<br />
CHENG UNIVERSITY<br />
Taiwan<br />
Tai-Wei Lan FUEL CYCLE AND<br />
MATERIAL<br />
ADMINISTRATION ATOMIC<br />
ENERGY COUNCIL<br />
Taiwan<br />
Chou Tzu-Hsing INSTITUTE OF NUCLEAR<br />
ENERGY RESEARCH<br />
Taiwan<br />
Tsong-Yang Wei<br />
Tajikistan<br />
INSTITUTE OF NUCLEAR<br />
ENERGY RESEARCH,<br />
AEC, TAIWAN<br />
Taiwan<br />
Dzhamshed Abdushukurov S.U.UMAROV PHYSICAL -<br />
TECHNICAL INSTITUTE<br />
OF ACADEMY OF SCIENCES<br />
Tajikistan<br />
OF REPUBLIC OF TAJIKISTAN<br />
Nazirzhon Buriev<br />
Ukraine<br />
S.U.UMAROV PHYSICAL -<br />
TECHNICAL INSTITUTE<br />
OF ACADEMY OF<br />
SCIENCES OF REPUBLIC<br />
OF TAJIKISTAN<br />
Tajikistan<br />
Olga Batyukhnova GUEST Ukraine<br />
Sergii Mitichkin<br />
United Kingdm<br />
CHERNOBYL NPP Ukraine<br />
Valerie Adsley GUEST United Kingdom<br />
Ian Adsley NUVIA LTD United Kingdom<br />
Andrew Baker EDEN NUCLEAR AND<br />
ENVIRONMENT LTD.<br />
United Kingdom<br />
Jonathan Baker CH2M HILL United Kingdom<br />
Tamara Baldwin GALSON SCIENCES<br />
LIMITED<br />
United Kingdom<br />
Angela Bartlett RESEARCH SITES<br />
RESTORATION LTD<br />
United Kingdom<br />
Robert Bonner URS United Kingdom<br />
Peter Booth WSP E&E United Kingdom<br />
Peter Burgess NUVIA LTD United Kingdom<br />
Andy Carr CALDER GROUP United Kingdom<br />
Iain Carvel RESEARCH SITES<br />
RESTOTATION LTD.<br />
United Kingdom<br />
Mike Cashin PORVAIR FILTRATION<br />
GROUP LTD<br />
United Kingdom<br />
Robert Clark NUVIA LIMITED United Kingdom<br />
Dan Curry URS United Kingdom<br />
Carol Darbyshire SPRINGFIELDS FUELS LTD United Kingdom<br />
Mike Davies NUVIA LIMITED United Kingdom<br />
Christopher Fisher OFFICE OF NUCLEAR<br />
REGULATION<br />
United Kingdom<br />
Lee Hartley SERCO United Kingdom<br />
Alan Heyes KING'S COLLEGE,<br />
LONDON United Kingdom<br />
Tim Hicks GALSON SCIENCES<br />
LIMITED United Kingdom<br />
Karl Hughes BABCOCK<br />
INTERNATIONAL United Kingdom<br />
Tim Hunter THE UNIVERSITY<br />
OF LEEDS<br />
United Kingdom<br />
Michael James SELLAFIELD LTD United Kingdom<br />
Steven Joyce SERCO United Kingdom<br />
Terry Kelly PAR SYSTEMS LTD United Kingdom<br />
Alastair Laird PROJECT TIME & COST United Kingdom<br />
Stephen Leclere SELLAFIELD LIMITED United Kingdom<br />
Angela Mackintosh SELLAFIELD LIMITED United Kingdom<br />
Ryan Maitland OFFICE FOR NUCLEAR<br />
REGULATION<br />
United Kingdom<br />
Simon Martin SELLAFIELD LTD United Kingdom<br />
John Mathieson NUCLEAR<br />
DECOMMISSIONING<br />
AUTHORITY<br />
United Kingdom<br />
Bill Miller AMEC United Kingdom<br />
Barry Moloney ENERGYSOLUTIONS United Kingdom<br />
Jenny Morris GALSON SCIENCES<br />
LIMITED<br />
United Kingdom<br />
Rachel O'donnell LLWR United Kingdom<br />
Michael Ojovan UNIVERSITY OF<br />
SHEFFIELD<br />
United Kingdom<br />
Alan Paulley QUINTESSA United Kingdom<br />
Philip Rendell NDA (RADIOACTIVE<br />
WASTE MANAGEMENT<br />
DIRECTORATE)<br />
United Kingdom<br />
Ian Richardson SELLAFIELD LIMITED United Kingdom<br />
David Rossiter LLW REPOSITORY LTD United Kingdom<br />
John Shevelan LLWR LTD United Kingdom<br />
Peter Sibley ENERGYSOLUTIONS United Kingdom<br />
Joe Small UK NATIONAL NUCLEAR<br />
LABORATORY<br />
United Kingdom<br />
Graham Smith GMS ABINGDON LTD United Kingdom<br />
Trevor Sumerling LLWR LTD United Kingdom<br />
Simon Thompson ENERGY SOLUTIONS United Kingdom<br />
Pippa Waterman ENERGYSOLUTIONS United Kingdom<br />
David Wells NUVIA LIMITED United Kingdom<br />
Stephen Wickham GALSON SCIENCES LTD United Kingdom<br />
Christopher Woodhead SA ROBOTICS LTD United Kingdom<br />
James Young<br />
United States<br />
UNIVERSITY OF LEEDS United Kingdom<br />
William Abramson LAWRENCE LIVERMORE<br />
NATIONAL LABORATORY<br />
United States<br />
Keith Anderson ECC United States<br />
Annabelle Axinn GUEST United States<br />
Ian Beadle AMEC United States<br />
Douglas Bablitch AMEC EARTH AND<br />
INRASTRUCTURE<br />
United States<br />
Gary Benda ICEM'11 CONFERENCE<br />
MANAGER<br />
United States<br />
Dianne Benda ICEM'11 GUEST TOURS United States<br />
Tiffany Blanchard USDOE / NATIONAL<br />
NUCLEAR<br />
United States<br />
James Blankenhorn PERMAFIX<br />
ENVIRONMENTAL<br />
SERVICES INC<br />
United States<br />
Joseph Boucau WESTINGHOUSE<br />
ELECTRIC COMPANY<br />
United States<br />
Laurel Boucher THE LAUREL CO. United States<br />
Shari Brabham CISS CORPORATION United States<br />
Pam Bradford CISS CORPORATION United States<br />
Kimberly Brewer ARS INTERNATIONAL, INC. United States<br />
Steven Brown SENES<br />
CONSULTANTS LTD<br />
United States<br />
Kathryn Brown GUEST United States<br />
Dwight Campbell CONTAINER PRODUCTS<br />
CORPORATION<br />
United States<br />
Mrs.Chapman GUEST United States<br />
Neil Chapman ARIUS ASSOCIATES United States<br />
Jean Pierre Cizel AREVA United States<br />
Gilles Clement AREVA BUVAL United States<br />
John Cochran SANDIA NATIONAL<br />
LABORATORIES<br />
United States<br />
Matthew Cole SA TECHNOLOGY United States<br />
Danny Coleman ARS INTERNATIONAL, INC. United States<br />
141
142<br />
ICEM'11 Pre-Registration Attendee List — By Country<br />
(Listed are only confirmed paid registrants as of 9-5-2011)<br />
Yvette Collazo U.S. DEPARTMENT United States<br />
OF ENERGY<br />
Carl Connell GUEST United States<br />
Judith Connell FLUOR United States<br />
Kevin Cook CERADYNE BORON United States<br />
PRODUCTS<br />
Michael Cournoyer LOS ALAMOS NATIONAL United States<br />
LABORATORY<br />
Michael Cull TELEDYNE BROWN United States<br />
ENGINEERING<br />
Mark Denton KURION, INC. United States<br />
Jas Devgun SARGENT & LUNDY United States<br />
Debbie Denton GUEST United States<br />
Michel Dilles AMTEK SAS United States<br />
Vince Dilworth ASME United States<br />
Nick DiMascio BARTLETT SERVICES INC. United States<br />
Paul Dixon LOS ALAMOS NATIONAL United States<br />
LABORATORY<br />
Mrs. Dixon Dixon GUEST Unites States<br />
Andrew Drom ENERGYSOLUTIONS United States<br />
EU LTD<br />
James Droppo PACIFIC NORTHWEST United States<br />
NATIONAL LABORATORY<br />
Tamar Droppo GUEST United States<br />
Felicia Durán SANDIA NATIONAL United States<br />
LABORATORIES<br />
Rateb (Boby) Abu-Eid U.S. NRC United States<br />
Andrew Edwards GUEST United States<br />
Amelia Fogleman GUEST United States<br />
Dyan Foss CH2M HILL PLATEAU United States<br />
REMEDIATION COMPANY<br />
Adam Foster STUDSVIK, INC. United States<br />
Patrick Gobert WESTINGHOUSE United States<br />
ELECTRIC COMPANY<br />
Rebecca Goddard GUEST United States<br />
Florence Goutelard CEA United States<br />
Achla Goyal GUEST United States<br />
Kapil Goyal LOS ALAMOS NATIONAL United States<br />
LABORATORY<br />
Steve Halliwell VJ TECHNOLOGIES, INC. United States<br />
Susan Hess AREVA United States<br />
Cathy Hickey CH2M HILL United States<br />
John Hollinden CONTAINER PRODUCTS United States<br />
CORPORATION<br />
David James DW JAMES United States<br />
CONSULTING, LLC<br />
Juanita James GUEST United States<br />
Steven Jameson STUDSVIK United States<br />
Danielle Jansik PACIFIC NORTHWEST United States<br />
NATIONAL LABORARY<br />
Angie Jones AMEC United States<br />
Sammy Jones GUEST United States<br />
Lawrence Judd NUVISION ENGINEERING United States<br />
Dawn Kaback AMEC GEOMATRIX United States<br />
Dennis Kelley PACIFI NUCLEAR United States<br />
SOLUTIONS<br />
Jeffrey Kerridge CH2M HILL United States<br />
Merry Keyser GUEST United States<br />
Ronald Keyser ORTEC United States<br />
Karen Kim ELECTRIC POWER United States<br />
RESEARCH INSTITUTE<br />
Heather Klebba NFT United States<br />
Kelly Knight BECHTEL NATIONAL, INC. United States<br />
Ken Kok ASME United States<br />
Paul Kreitman WESTINGHOUSE United States<br />
NUCLEAR SERVICES<br />
Albert Kruger US DOE United States<br />
Barbara Larsen GUEST Unites States<br />
Gerard Laurent EDF/CIDEN United States<br />
John Lehew CH2M HILL PLATEAU United States<br />
REMEDIATION COMPANY<br />
Yung Liu ARGONNE NATIONAL United States<br />
LABORATORY<br />
Jeffrey Lively AMEC United States<br />
Juliann Maffett EDGEN MURRAY United States<br />
Keith McConnell U.S. NUCLEAR United States<br />
REGULATORY<br />
COMMISSION<br />
Betty Meyer GUEST United States<br />
Greg Meyer FLUOR GOVERNMENT United States<br />
GROUP<br />
Ross Miller SANDIA NATIONAL United States<br />
LABORATORIES<br />
Ronald Morris WESTINGHOUSE United States<br />
ELECTRIC COMPANY USA<br />
Mark Morton WORLEYPARSONS United States<br />
POLESTAR<br />
Virginia Morton GUEST United States<br />
Gary Mottershead VJ TECHNOLOGIES, INC. United States<br />
Ronnie Mulligan GUEST United States<br />
Virgene Mulligan ARS INTERNATIONAL United States<br />
Tracy Mustin U.S. DEPARTMENT United States<br />
OF ENERGY<br />
Gus Myers BABCOCK SERVICES INC. United States<br />
Mike Nichols PACTEC EPS LTD. United States<br />
William Nutt ARGONNE NATIONAL United States<br />
LABORATORY<br />
Donald Olson COLUMBIANA HI TECH United States<br />
Jean-Jacques Peraudin GEOVARIANCES<br />
Geoffrey Peter OREGON INSTITUTE OF United States<br />
TECHNOLOGY<br />
PORTLAND CAMPUS<br />
Martin Plys FAUSKE & United States<br />
ASSOCIATES, LLC<br />
Edward Posivak WMG, INC. United States<br />
John Proni FLORIDA United States<br />
INTERNATIONAL<br />
UNIVERSITY<br />
Maria Elena Proni GUEST United States<br />
Rosa Ramirez U.S. DEPARTMENT United States<br />
OF ENERGY<br />
John Raymont KURION, INC. United States<br />
Marilyn Raymont GUEST United States<br />
Reginald Recco AMETEK SAS United States<br />
Steve Rima AMEC United States<br />
Bernard Rottner ONET TECHNOLOGIES United States<br />
James Russell NEVADA NATIONAL United States<br />
SECURITY SITE<br />
Mike Sanchez PACTEC, INC. United States<br />
Richard Schwent GUEST United States<br />
Bill Shingler FLUOR GOVERNMENT United States<br />
GROUP<br />
Jager Smith ENTERGY United States<br />
Janet Smith GUEST United States<br />
Dawn Stevens GUEST United States<br />
Howard Stevens STUDSVIK, INC. United States<br />
Bryan Swinson PAJARITO SCIENTIFIC United States<br />
CORPORATION<br />
Bernard Vignau CEA SACLAY United States<br />
Charles Waggoner INSTITUTE FOR United States<br />
CLEAN ENERGY<br />
TECHNOLOGY<br />
Jeroen Welbergen COVRA N.V. United States<br />
Craig Williamson SOUTH CAROLINA United States<br />
RESEARCH AND<br />
EDUCATION FOUNDATION<br />
Bertrand Willmann AREVA United States<br />
Keith Witwer IMPACT SERVICES, INC., United States<br />
GEOMELT DIVISION
Technical <strong>Program</strong> Organizers<br />
TRACK CO-CHAIRS<br />
TECHNICAL PROGRAM CO-CHAIRS<br />
Gary Benda, Bartlett Services, Inc. (USA) and Dominique Grenêche, Consultant (FRANCE)<br />
TRACK 1<br />
Low/Intermediate-Level (L/ILW) Radioactive Waste Management<br />
Angie Jones, AMEC (USA), Michel Dutzer, Andra (France), Jerome Brueziere, CEA (France), Marc Butez, CEA (France),<br />
Christopher Joussot-Dubien, CEA (France)<br />
TRACK 2<br />
Spent Fuel, Fissile Material, Transuranic (TRU) and High-Level Radioactive Waste (HLW) Management<br />
Heather Klebba, Nuclear Filter Technology (USA), Gerald Ouzounian, Andra (France)<br />
TRACK 3<br />
Facility Decontamination and Decommissioning (D&D)<br />
Jas Devgun, Sargent & Lundy (USA), Jean-Guy Nokhamzon, CEA (France), Thierry Varet, AREVA – BU Value (France)<br />
TRACK 4<br />
Environmental Remediation (ER)<br />
Steve Brown, Senes Consultants (USA), Didier Dubot, CEA (France), Sandrine Magdaliniuk, AREVA (France),<br />
Jean-Guy Nokhamzon, CEA/DEN/DADN (France)<br />
TRACK 5<br />
Environmental Management (EM)/Public Involvement/Crosscutting Issues/Global Partnering<br />
Judith (Judy) Connell, Fluor (USA), Regis Dalmas, EDF (France), Yvette Collazo, US DOE (USA)<br />
Ana Han, US DOE (USA), Jim Marra, US DOE (USA), Gerald Ouzounian, Andra (France),<br />
Jean-Guy Nokhamzon, CEA/DEN/DADN (France)<br />
Session Organizers<br />
Keith Anderson, ECC (USA)<br />
Johan Andersson, JA Streamflow AB (Sweden)<br />
Andrew Baker, Eden Nuclear and Environment Ltd. (UK)<br />
Ian Beadle, AMEC (UK)<br />
Gary Benda, Bartlett Services (USA)<br />
Ed Bentz, EJ Bentz & Associates (USA)<br />
Paul Black, Neptune and Company Inc (USA)<br />
James Blankenhorn, Perma-Fix (USA)<br />
Steve Brown, SENES Consultants Ltd (USA)<br />
Jerome Brueziere, AREVA (France)<br />
Sean Bushart, Electric Power Research Institute (USA)<br />
Jean Paul Chiles, Ecole Mines (France)<br />
Hans Codee, Corva (Netherlands)<br />
Judith (Judy) Connell, Fluor (USA)<br />
Yvette Collazo, US DOE (USA)<br />
Ian Crossland, Crossland Consulting (UK)<br />
Jean-Marie Cuchet, BELGONUCLEAIRE (Belgium)<br />
Michael Cull, Teledyne (USA)<br />
Didier Delmont, CEA (France)<br />
Mark Denton, Kurion Inc. (USA)<br />
Jas Devgun, Sargent & Lundy(USA)<br />
Didier Dubot, CEA/FAR/USLT/SPRE/SAS (France)<br />
Michel Dutzer, Andra (France)<br />
Kapila Fernando, ANSTO (Australia)<br />
Dominique Francois-Bongarcon, AGORATEK<br />
International Consultants (Canada)<br />
Mike Garamszeghy, Nuclear Waste Management<br />
Organization (Canada)<br />
Irina Gaus, Nagra (Switzerland)<br />
Dominique Greneche, Consultant (France)<br />
Mark Gerchikov, AMEC (Canada)<br />
Donald Goebel, SEC (USA)<br />
Jeffrey Griffin, SRNL (USA)<br />
Ana Han, US DOE (USA)<br />
Paul Haigh, The Paul Haigh Partnership (UK)<br />
Cathy Hickey, CH2M Hill (USA)<br />
Jean-Michel Hoorelbeke, ANDRA (France)<br />
Natraj Iyer, SRNL (USA)<br />
Angie Jones, AMEC (USA)<br />
Heather Klebba, NFT (USA)<br />
Ronald Keyser, ORTEC - AMETEK (USA)<br />
John Mathieson, NDA (UK)<br />
Vicki Maranville, AMEC (UK)<br />
Jim Marra, US DOE (USA)<br />
Adrian Mendez-Torres, SRNL (USA)<br />
Bill Miller, AMEC (UK)<br />
Horst Monken Fernandes, IAEA (Austria)<br />
Jean-Guy Nokhamzon, CEA/DEN/DADN (France)<br />
Karan North, Magnox Ltd (UK)<br />
Michael Ojovan, University of Sheffield (UK)<br />
Peter Ormai, IAEA (Austria)<br />
Gerald Ouzounian, Andra (France)<br />
Corhyn Parr, Nuclear Enterprises (UK)<br />
Kanwar Raj, Bhabha Atomic Research Center (India)<br />
Philip Rendell, NDA (UK)<br />
Hans Riotte, OECD/NEA (France)<br />
Roger Seitz, SRNL (USA)<br />
Andy Szilagyi, US DOE (USA)<br />
Anibal Taboas, Consultant (USA)<br />
Patricia Torres, ANDRA (France)<br />
Walter Van Hecke, AREVA (France)<br />
Leo Van Velzen, NRG (Netherlands)<br />
Thierry Varet, AREVA (France)<br />
Bill Wilmarth, SRNL (USA)<br />
David Wallace, CDM (USA)<br />
Susan Walter, AECOM (USA)<br />
Stephen Wickham, Galson Sciences Limited (UK)<br />
Robert Zelmer, Atomic Energy of Canada Limited (Canada)<br />
143
144<br />
Conference Steering Committee<br />
General Co-Chairs<br />
Anibal Taboas, Consultant<br />
Dominique Grenêche, Consultant<br />
Conference Manager<br />
Gary Benda, Bartlett Services<br />
ICEM Project Director<br />
Vince Dilworth, ASME<br />
European Event Manager<br />
Bernard Jolly, French Nuclear Energy Society (SFEN)<br />
Technical Paper Submission; Abstracts, Bio's, Copyright, Drafts and/or <strong>Final</strong> Papers<br />
Stacey Cooper, ASME<br />
Shari Brabham, CISS Corporation<br />
US <strong>Program</strong> Coordinator for the Technical <strong>Program</strong>, Non-Eu Conference Registration or Non-European<br />
Union Vendor Exhibition<br />
Shari Brabham, CISS Corporation<br />
EU Coordinator for Reims, France and Other Local Aspects, Conference Facilities, Social <strong>Program</strong>s, Vendor<br />
Arrangements, European Union (EU) Vendor Exhibition or EU Conference Registrations<br />
Sylvie Delaplace, French Nuclear Energy Society (SFEN)<br />
Technical Tours<br />
Sylvie Delaplace, French Nuclear Energy Society (SFEN)<br />
US Federal Liaison(s)<br />
Yvette Collazo, US Department of Energy<br />
Larry Camper US Nuclear Regulatory Commission<br />
EU Liaison(s)<br />
Bernard Jolly, French Nuclear Energy Society (SFEN)<br />
IAEA Liaison<br />
Irena Mele, IAEA, Division of Nuclear Fuel Cycle and Waste Technology<br />
ASME ICEM'11 Conference Committee Liaisons<br />
Vincent Dilworth, ASME<br />
Anibal Taboas, Consultant, Environmental Engineering Division<br />
Ken Kok, Consultant, Nuclear Engineering Division<br />
French Nuclear Energy Society (SFEN)<br />
Bernard Jolly, French Nuclear Energy Society (SFEN)
Schedule of <strong>Events</strong><br />
— SUNDAY, SEPTEMBER 25, 2011 —<br />
Event Time Location<br />
Golf Tournament 7:30am - 3:00pm Le Golf de Reims Champagne<br />
Technical Training Course 9:00am - 4:00pm RCC - Room 5, 2nd Floor<br />
Exhibitor Set Up 2:00pm - 8:00pm RCC - Exhibition Hall, 1st Floor<br />
Registration 4:00pm - 7:00pm RCC - Foyer, 1st Floor<br />
Author/Panelist/Co-Chair Check-in 4:00pm - 7:00pm RCC - Foyer, 1st Floor<br />
Speakers Ready Area 4.00pm - 7:00pm RCC - Salle De Presse, 2nd Floor<br />
Welcome Reception 6:00pm - 8:00pm RCC - “Le Bouchon” Space, 2nd Floor<br />
— MONDAY, SEPTEMBER 26, 2011 —<br />
Event Time Location<br />
Registration 7:15am - 6:00pm RCC - Foyer, 1st Floor<br />
Author/Panelist/Co-Chair Check-in 7:15am - 6:00pm RCC - Foyer, 1st Floor<br />
Speakers Ready Area 7:15am - 5:00pm RCC - Salle De Presse, 2nd Floor<br />
Speakers Briefing 7:30am - 8:00am RCC - “Le Millesime” Space, 1st Floor<br />
Guest Welcome Reception 8.00am - 9:00am RCC - Room 1, 2nd Floor<br />
Coffee Service - Pre Opening Session 8:00am - 9:00am RCC - “Le Bouchon” Space, 2nd Floor<br />
Exhibitor Set up 8:00am - 11:00am RCC - Exhibition Hall, 1st Floor<br />
Monday Morning Opening Session 9:00am - 12:30pm RCC - Salle Royale, 2nd Floor<br />
Coffee Break After 3rd Speaker RCC - “Le Bouchon” Space, 2nd Floor<br />
Poster Session 9 12:00pm - 5:45pm RCC - Exhibition Hall, 1st Floor<br />
Exhibition Open 12:00pm - 6:00pm RCC - Exhibition Hall, 1st Floor<br />
Lunch Break 12:30pm - 1:40pm RCC - Exhibition Hall, 1st Floor<br />
Sessions 2 - 8 1:45pm - 6:00pm RCC - Rooms 1 - 10, 2nd Floor<br />
Coffee Break 3:30pm - 4:10pm RCC - Exhibition Hall, 1st Floor<br />
— TUESDAY, SEPTEMBER 27, 2011 —<br />
Event Time Location<br />
Speakers Ready Area 7:15am - 5:00pm RCC - Salle De Presse, 2nd Floor<br />
Registration 7:15am - 6:00pm RCC - Foyer, 1st Floor<br />
Author/Panelist/Co-Chair Check-in 7:15am - 6:00pm RCC - Foyer, 1st Floor<br />
Speakers Briefing 7:30am - 8:00am RCC - “Le Millesime” Space, 1st Floor<br />
Exhibit Hall Hours 8:30am - 8:00pm RCC - Exhibition Hall, 1st Floor<br />
Sessions 10 - 18 8:30am - 12:30pm RCC - Rooms 1 - 10, 2nd Floor<br />
Poster Session 19 8:30am - 5:45pm RCC - Exhibition Hall, 1st Floor<br />
Coffee Break 10:15am - 10:40am RCC - Exhibition Hall, 1st Floor<br />
Lunch Break 12:30pm - 1:40pm RCC - Exhibition Hall, 1st Floor<br />
Sessions 20 - 28 1:45pm - 6:00pm RCC - Rooms 1 - 10, 2nd Floor<br />
Coffee Break 3:30pm - 4:10pm RCC - Exhibition Hall, 1st Floor<br />
Tuesday Exhibit Reception 6:00pm - 8:00pm RCC - Exhibition Hall, 1st Floor<br />
— WEDNESDAY, SEPTEMBER 28, 2011 —<br />
Event Time Location<br />
Speakers Ready Area 7:15am - 5:00pm RCC - Salle De Presse, 2nd Floor<br />
Registration 7:15am - 6:00pm RCC - Foyer, 1st Floor<br />
Author/Panelist/Co-Chair Check-in 7:15am - 6:00pm RCC - Foyer, 1st Floor<br />
Speakers Briefing 7:30am - 8:00am RCC - “Le Millesime” Space, 1st Floor<br />
Sessions 29- 38 8:30am - 12:30pm RCC - Rooms 1 - 10, 2nd Floor<br />
Exhibit Hall Hours 8:30am - 5:00pm RCC - Exhibition Hall, 1st Floor<br />
Poster Session 39 8:30am - 5:45pm RCC - Exhibition Hall, 1st Floor<br />
Coffee Break 10:15am - 10:40am RCC - Exhibition Hall, 1st Floor<br />
Lunch Break 12:30pm - 1:40pm RCC - Exhibition Hall, 1st Floor<br />
Sessions 40 – 49 1:45pm - 6:00pm RCC - Rooms 1 - 10, 2nd Floor<br />
Coffee Break 3:30pm - 4:10pm RCC - Exhibition Hall, 1st Floor<br />
Wednesday Banquet 7:30pm - 11:30 pm Champagne De Castelnau Caveau<br />
— THURSDAY, SEPTEMBER 29, 2011 —<br />
Event Time Location<br />
Registration 7:15am - 12:30pm RCC - Foyer, 1st Floor<br />
Speakers Ready Area 7:15am - 12:30pm RCC - Salle De Presse, 2nd Floor<br />
Author/Panelist/Co-Chair Check-in 7:15am - 1:00pm RCC - Foyer, 1st Floor<br />
Speakers Briefing 7:30am - 8:00am RCC - “Le Millesime” Space, 1st Floor<br />
Exhibit Hall Hours 8:30am - 11:00am RCC - Exhibition Hall, 1st Floor<br />
Poster Session 60 8:30am - 11:00am RCC - Exhibition Hall, 1st Floor<br />
Sessions 50 – 59 8:30am - 12:30pm RCC – Rooms 1 - 10, 2nd Floor<br />
Coffee Break 10:15am - 10:40am RCC - Exhibition Hall, 1st Floor<br />
Conference Ends 12:30pm RCC - 1st Floor<br />
— FRIDAY, SEPTEMBER 30, 2011 —<br />
Event Time Location<br />
Technical Tours Departure 7:00am Departs RCC