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Session 37-38 Abstracts cal uncertainty of the fitted parameters and thus the error in the derived depth. <strong>The</strong> paper describes the contributing effects of the inherent prop- Address all correspondence to this author. erties of each detector; effects such as their energy resolution, absolute efficiency as well as peak-to-Compton ratio. Finally a commentary on the applicability of each selected detector type is presented, including a comment on the extension the technique to a more generic, real world solution. 8) REMOTE MEASUREMENTS OF RADIOACTIVITY DISTRIBUTION WITH BROKK ROBOTIC SYSTEM - 16147 Oleg Ivanov, Alexey Danilovich, Vyacheslav Stepanov, Sergey Smirnov, Victor Potapov, RRC Kurchatov Institute (Russia) Robotic system for the remote measurement of radioactivity in the reactor areas was developed. <strong>The</strong> BROKK robotic system replaces hand-held radiation measuring tools. <strong>The</strong> system consists of a collimated gamma detector, a standard gamma detector, color CCD video camera and searchlights, all mounted on a robotic platform (BROKK). <strong>The</strong> signals from the detectors are coupled with the video signals and are transferred to an operator’s console via a radio channel or a cable. Operator works at a safe position. <strong>The</strong> video image of the object with imposed exposure dose rate from the detectors generates an image on the monitor screen, and the images are recorded for subsequent analysis. Preliminary work has started for the decommissioning of a research reactor at the RRC «Kurchatov Institute». Results of the remote radioactivity measurements with new system during radiation inspection waste storage of this reactor are presented and discussed. 9) RADIOLOGICAL CHARACTERISATION THROUGHOUT THE UK NUCLEAR INDUSTRY - 16300 Chris Hannon, Studsvik UK (UK) Radiological Characterisation is the technique of determining the radiological properties of a material using a combination of studying the materials history, in-situ measurements and intrusive sampling. To consign radioactive waste from a site in the UK knowledge of the wastes radiological content is required. Intermediate Level Waste (ILW), Low Level Waste (LLW), exempt and excluded materials all require characterisation to different degrees and certainty. Effective radiological characterisation will determine the most suitable waste treatment or disposal route. Money spent by a project on characterisation up front will be recouped in the long term by efficient waste sentencing. <strong>The</strong> first step in any campaign of radiological characterisation is to study the available information relating to the history of the waste. By carefully studying the history of he waste the most likely waste treatment/disposal routes can be identified and the most applicable types of in-situ measurements or intrusive sampling can be derived. Whilst it is not uncommon to have little or no reliable historic information a logical and defensible hypothesis of the wastes likely classification can streamline the characterisation project. However care must always be taken to not limit the types of measurements that will be undertaken so as to limit the risk of missing some hard to measure radionuclides. SESSION 38 - SITING, DESIGN, CONSTRUCTION, AND OPERATION OF L/ILW DISPOSAL FACILITIES 1) DESIGN OPTIONS FOR THE UKS ILW GEOLOGICAL DISPOSAL FACILITY - 16241 Tim Hicks, Matt White, Tamara Baldwin, Paul Hooker, Phil Richardson, Galson Sciences Ltd (UK); Neil Chapman, Chapman & Co. Consulting (Switzerland); Fiona Neall, Neall Consulting Ltd (UK); Ian McKinley, McKinley Consulting (Switzerland); Samantha King, NDA RWMD, (UK) Over the last few years, a major national programme of public consultation has been under way in the UK resulting, in 2006, in the announcement by government of geological disposal as the most appropriate solution for the long-term management of the UKs long-lived and higher-activity radioactive waste and the launch, in 2008, of an implementation programme. <strong>The</strong> approach being pursued is to solicit volunteer communities to host a geological disposal facility, which may contain not only intermediatelevel waste (ILW) and some low-level waste (LLW), but also high-level waste (HLW), any spent fuel (SF) declared as waste, and potentially other materials that may be declared as waste. <strong>The</strong>se wastes have different physical, chemical, thermal and radiological characteristics, and different concepts will be required to accommodate their disposal, potentially in a single facility. <strong>The</strong> volunteer approach means that the geological environment that might eventually emerge as the preferred location is not known at the outset. Indeed, the siting process may require evaluation of several different geological environments because the UK has rich geological variability for such a small landmass. Consequently, the Nuclear Decommissioning Authority (NDA), which is charged with designing, developing and implementing a geological disposal facility, has investigated facility designs that could be appropriate for a wide range of host rocks and geological environments. 2) LESSONS LEARNED FROM THE OPERATION OF A L/ILW NATIONAL DISPOSAL CENTRE: THE CABRIL AND THE SPANISH CASE - 16029 Emilio Garcia Neri, Mariano Navarro, Fernando Gomez,ENRESA (Spain) <strong>The</strong> Spanish experience holds a relatively important position in the field of the LILW management. <strong>The</strong> management of LILW in Spain can be defined as an integrated system that includes from the controls of production and the collection and transport of LILW to its disposal. In this system, the clear definition of the responsibilities of each one of the actors has a fundamental paper. ENRESA, the Radioactive Waste Management Organisation in Spain, operates the El Cabril centre from 1993, being this installation a key component for the National LILW management programme. Throughout these years, ENRESA is accumulated a significant operational experience from a multidisciplinary point of view, that includes technical, economic and social aspects. From his phase of design to today, passed already more than fifteen years, ENRESA has adopted a series of decisions and developed programs and activities that have allowed the evolution of the own installation until the reality that is today. This paper intends to present the lessons learned through this experience from a strategic perspective on more relevant and significant aspects that they have facilitated the normal operation of the installation and the development of specific solutions to the challenges proposed by the development of the activities and the new needs of the Spanish programme. 108
Abstracts Session 38 3) HYDROGEOLOGIC MODELLING IN SUPPORT OF A PROPOSED DEEP GEOLOGIC REPOSITORY IN CANADA FOR LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTE - 16264 Jonathan Sykes, Stefano Normani, Yong Yin, University of Waterloo (Canada); Eric Sykes, Mark Jensen, Nuclear Waste Management Organization (Canada) A Deep Geologic Repository (DGR) for Low and Intermediate Level radioactive waste has been proposed by Ontario Power Generation for the Bruce Nuclear Power Development site in Ontario, Canada. <strong>The</strong> DGR is to be constructed at a depth of about 680 m below ground surface within the argillaceous Ordovician limestone of the Cobourg Formation. This paper describes a regional-scale geologic conceptual model for the DGR site and analyzes flow system evolution using the FRAC3DVS-OPG flow and transport model. This provides a framework for the assembly and integration of site-specific geoscientific data that explains and illustrates the factors that influence the predicted long-term performance of the geosphere barrier. In the geologic framework of the Province of Ontario, the Bruce DGR is located at the eastern edge of the Michigan Basin. Borehole logs covering Southern Ontario combined with site specific data have been used to define the structural contours at the regional and site scale of the 31 sedimentary strata that may be present above the Precambrian crystalline basement rock. <strong>The</strong> regional-scale domain encompasses an 18,500 km2 region extending from Lake Huron to Georgian Bay. <strong>The</strong> groundwater zone below the Devonian is characterized by units containing stagnant water having high concentrations of total dissolved solids that can exceed 300 g/l. <strong>The</strong> computational sequence involves the calculation of steady-state density independent flow that is used as the initial condition for the determination of pseudo-equilibrium for a density dependent flow system that has an initial TDS distribution developed from observed data. Long-term simulations that consider future glaciation scenarios include the impact of ice thickness and permafrost. <strong>The</strong> selection of the performance measure used to evaluate a groundwater system is important. <strong>The</strong> traditional metric of average water particle travel time is inappropriate for geologic units such as the Ordovician where solute transport is diffusion dominant. <strong>The</strong> use of life expectancy and groundwater age is a more appropriate metric for such a system. <strong>The</strong> mean life expectancy for the DGR and base case parameters has been estimated to be in excess of 8 million years. 4) I-GRAPHITE WASTE MANAGEMENT IN FRANCE - 16301 Odile Ozanam, Gerald Ouzounian, ANDRA (France) In France about 23,000 tons of irradiated graphite waste were generated mainly from 9 nuclear gas-cooled reactors (UNGG type). All these reactors are now shut down. In France, a final disposal route has been decided for i-graphite waste management by the French Parliament in 2006. <strong>The</strong> planning act of June 28, 2006 has provisioned that a research and investigation programme shall be established with a view to developing disposal options for graphite waste. <strong>The</strong> low specific activity of these wastes means shallow disposal facilities located in a geological layer with a low permeability. <strong>The</strong> main radionuclides that need specific attention for the long term safety are Chlorine 36 and Carbon 14. This establishes the main requirements for the graphite disposal. According to these requirements, underground disposal in a clay layer, at shallow depth, offers good performance in terms of the delay and the reduction of the radionuclide release; it also offers guarantees for the cover’s hydrodynamic and transport properties. <strong>The</strong> progress of the programme makes it now necessary for a site to be found. Based on a bibliographical study, a wide-spread call for applications took place during the second semester of 2008. 5) INDUSTRIAL COMPLEX FOR SOLID RADWASTE MANAGEMENT (ICSRM) AT CHERNOBYL NUCLEAR POWER PLANT FUNCTIONALITY OF THE FACILITIES - EXPERIENCE OF PROJECT EXECUTION - 16057 Heiko Eichhorn, NUKEM Technologies GmbH (Germany) After an international tendering process NUKEM was awarded to build the Industrial Complex for Solid Radwaste Management (ICSRM) at the Chernobyl Nuclear Power Plant. <strong>The</strong> ICSRM consists of four facilities (LOT): Lot 0: SLWS (Solid and Liquid Waste Storage) It is an interim storage facility for intermediate and high level long-lived radioactive waste in an existing building at ChNPP site. This building has been refurbished and modified to accommodate the required equipment. LOT 0 was handed over to the Employer June 2007 LOT 1: A solid waste retrieval facility, comprising the installation of a retrieval facility for operational Low and Intermediate Level Short-Lived Waste (LILW-LL/SL) and High Level Waste (HLW) currently stored in the existing storage silo. Due to the Chernobyl accident, this storage also contains an unknown percentage of Long-Lived (LL) waste. LOT 1 was handed over to the Employer in April 2009. LOT 2: solid waste processing plant, comprising a plant for the sorting and segregation of all categories of solid radwaste and the processing of the solid LILW-LL/SL generated from the previous retrieval activities (LOT 1) and from the routine operational and decommissioning activities of the ChNPP. LILW-SL will be packaged and immobilized for removal to the near surface disposal facility (LOT 3) whilst higher category wastes (LILW-LL and HLW) will be packaged, over-packed and stored in a temporary storage facility (SLWS) while awaiting the construction of an interim storage facility. LOT 2 is handed over to the Employer in April 2009. LOT 3: repository for the disposal of short-lived waste, comprising a near surface repository in accordance with the requirements of the Ukrainian Nuclear Regulatory Authorities and in the form of an engineered facility for the final disposal of LILW-SL conditioned in LOT 2 and for wastes from the Liquid Radwaste Treatment Plant (LRTP) currently being build on Chernobyl NPP site. <strong>The</strong> facility will maintain its integrity during 300-year instutional control period. LOT 3 was handed over to the Employer in December 2007. 6) EXPERIENCES RELATED TO THE DEVELOPMENT OF A HIGH VOLUME VERY LOW LEVEL WASTE DISPOSAL FACILITY IN THE UK - 16371 Andy Baker, Andy Baker Consulting Ltd (UK); Andrea Borwick,WRG (UK); KayLin Loveland, Adam Meehan, Mike Travis, EnergySolutions (UK); Ian Warner, Magnox North Ltd (UK) New Government policy regarding waste disposal suggests that a wider range of options should be evaluated for the management of low-level waste (LLW), including disposal to landfill. A new sub-category was created for nuclear industry waste disposal: high-volume very low level waste (HV VLLW). <strong>The</strong> Government has stated that it expects the majority of waste in this category that could go to landfill would consist of rubble and soil from decommissioning activities. This category would contain only small amounts of radioactivity and can be safely disposed to landfill, subject to appropriate controls. 109
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FINAL PROGRAM ICEM’09/ DECOM’09
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Table of Contents ICEM’09/DECOM
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Transportation by Ferry to Liverpoo
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Conference Registr
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gram to provide guidance on selecti
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Notes 9
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Liverpool City Center Map Bus Loadi
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Condensed Conference</stron
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SESSION # Technical Program at a Gl
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Technical Sessions Monday PM SESSIO
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Technical Sessions Tuesday AM SESSI
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Technical Sessions Tuesday AM 2. Ri
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Technical Sessions Tuesday PM Seide
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Technical Sessions Wednesday AM Wed
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Technical Sessions Wednesday AM SES
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Technical Sessions Wednesday PM 4.
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Technical Sessions Thursday AM SESS
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Exhibitors Listings We would like t
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ATKINS STAND: 32 Contact: Nigel Tho
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emote operations. Our background of
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GOLDSIM STAND: 58 TECHNOLOGY GROUP
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JFIMS & JFN STAND: 67 Contact: JFIM
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ased system. Our professional staff
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assembled a team whose guiding prin
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demanding clients, and we also offe
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management, and technical consultan
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Page 61 and 62: Abstracts Session 4 The</st
Page 63 and 64: Abstracts Session 5-6 ically made o
Page 65 and 66: Abstracts Session 7-8 Brief descrip
Page 67 and 68: Abstracts Session 9 3) SHARED, REGI
Page 69 and 70: Abstracts Session 10-12 The
Page 71 and 72: Abstracts Session 12 joint awarenes
Page 73 and 74: Abstracts Session 15 SESSION 15 - D
Page 75 and 76: Abstracts Session 16 2) STRATEGIC P
Page 77 and 78: Abstracts Session 17 3) DESIGN OF P
Page 79 and 80: Abstracts Session 18 After the eval
Page 81 and 82: Abstracts Session 19 SESSION 19 - G
Page 83 and 84: Abstracts Session 22 SESSION 22 - P
Page 85 and 86: Abstracts Session 22 The</s
Page 87 and 88: Abstracts Session 24 Currently, of
Page 89 and 90: Abstracts Session 25-26 During the
Page 91 and 92: Abstracts Session 27 conditions pre
Page 93 and 94: Abstracts Session 28 posal of spent
Page 99 and 100: Abstracts Session 31 5) INTERDIGITA
Page 101 and 102: Abstracts Session 33 SESSION 33 - D
Page 103 and 104: Abstracts Session 34 D) FURTHER DEV
Page 105 and 106: Abstracts Session 34-36 TcO2(s). Fo
Page 107 and 108: Abstracts Session 36 4) PRELIMINARY
Page 109: Abstracts Session 37 4) ENVIRONMENT
Page 115 and 116: Abstracts Session 41 mined in an an
Page 117 and 118: Abstracts Session 43 radioactivity
Page 119 and 120: Abstracts Session 45 testing and op
Page 121 and 122: Abstracts Session 48 As a result of
Page 123 and 124: Abstracts Session 49-50 A novel met
Page 125 and 126: Abstracts Session 51 ings require m
Page 127 and 128: Abstracts Session 52-54 reflects ev
Page 129 and 130: Abstracts Session 55 It is found th
Page 131 and 132: Abstracts Session 56-57 2) A TRULY
Page 133 and 134: Abstracts Session 58 2) A SUCCESSFU
Page 135 and 136: Abstracts Session 59-60 4) SAFETY E
Page 137 and 138: Abstracts Session 61 According to r
Page 139 and 140: Abstracts Session 62-63 4) BIOAVAIL
Page 141 and 142: Abstracts Session 63 6) FORMATION O
Page 143 and 144: Pre-Registered Attendees by Country
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Page 151: Convention Center — Cross Section
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