The 12th International Conference on Environmental ... - Events
The 12th International Conference on Environmental ... - Events
The 12th International Conference on Environmental ... - Events
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Sessi<strong>on</strong> 20-21 Abstracts<br />
SESSION 20 - PANEL: GLOBAL PARTNERING IN INTERNATIONAL WASTE AND CLEANUP PROGRAMS<br />
ABSTRACTS NOT REQUIRED<br />
SESSION 21 - ENVIRONMENTAL MANAGEMENT HEALTH AND SAFETY ISSUES<br />
1) DOSE ASSESMENT OF PERSONNEL HANDLING CONDITIONED RADIOACTIVE WASTE - 16149<br />
Michal Panik, Matej Zachar, Vladimir Necas, Slovak University of Technology in Bratislava (Slovakia)<br />
Radioactive waste may arise throughout the lifetime of any type of nuclear facility. This waste has to be isolated from the envir<strong>on</strong>ment<br />
using the engineered and natural barriers of near surface or deep geological radioactive waste repository. Before final disposal,<br />
the waste volume is reduced in the treatment process and then it is immobilized into the stable matrix.<br />
In Slovakia, the treated radioactive waste is c<strong>on</strong>diti<strong>on</strong>ed into fibre-reinforced c<strong>on</strong>crete c<strong>on</strong>tainers using a cementati<strong>on</strong> technology.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>se c<strong>on</strong>tainers are the <strong>on</strong>ly overpacks approved for near surface disposal in the Nati<strong>on</strong>al Radioactive Waste Repository located<br />
at Mochovce nuclearsite (Slovakia). Every filled c<strong>on</strong>tainer has to fulfill the defined limits and c<strong>on</strong>diti<strong>on</strong>s for safe transport and<br />
disposal. <str<strong>on</strong>g>The</str<strong>on</strong>g> dose parameters, determining the safety of pers<strong>on</strong>nel handling a c<strong>on</strong>tainer, are <strong>on</strong>e of them. Basically, the doses are<br />
measured <strong>on</strong> the c<strong>on</strong>tainer walls` outer surfaces and <strong>on</strong> the lid of the c<strong>on</strong>tainer. <str<strong>on</strong>g>The</str<strong>on</strong>g> dose m<strong>on</strong>itoring in 1 meter distance from the<br />
c<strong>on</strong>tainer walls and from the lid of the c<strong>on</strong>tainer is performed before transportati<strong>on</strong> as well.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> calculati<strong>on</strong> code VISIPLAN 3D ALARA is a planning tool and it calculates dose parameters also for the above menti<strong>on</strong>ed<br />
positi<strong>on</strong>s c<strong>on</strong>cerning the fibre-reinforced c<strong>on</strong>crete c<strong>on</strong>tainer which c<strong>on</strong>tains waste with different physical or radiological characteristics.<br />
In the paper, calculated data are compared with in-situ measurements. Using VISIPLAN 3D ALARA planning tool, various<br />
scenarios are evaluated. Finally, the Under the Global Partnership Initiative and in resp<strong>on</strong>se to a Russian government request, the<br />
Federal Government of Canada launched a program to dismantle Russian Federati<strong>on</strong> Nuclear-Powered Submarines (NPS). In July<br />
2004, Canada initiated a bilateral program for the dismantlement of 12 general purpose NPS in the Zvyozdochka shipyard in<br />
Severodvinsk. Following successful completi<strong>on</strong> of this program in March 2008, Canada initiated a sec<strong>on</strong>d NPS dismantling program<br />
at the Zvezda shipyard in the Russian Far East.<br />
2) RISK ANALYSIS AND COST-BENEFIT ANALYSIS OF REMEDIAL ACTIONS<br />
IN THE CENTRAL ASIA: AMYDARYA AND SYRDARYA RIVERS BASINS<br />
TRANSBOUNDARY POLLUTION DUE TO URANIUM-MINING INDUSTRY - 16187<br />
Vladimir Georgievskiy, Russian Research Center “Kurchatov Iinsitute” (Russia)<br />
In this Report are c<strong>on</strong>sidered some aspects of the analysis of c<strong>on</strong>sequences of uranium-mining industry in the Central Asia.<br />
1. <str<strong>on</strong>g>The</str<strong>on</strong>g> risk analysis is c<strong>on</strong>sidered in terms of collective effective commitment dose.<br />
2. It is proposed the general estimati<strong>on</strong> of risk (collective effective commitment dose) for the Central Asia from tailings piles<br />
as a result of uranium mining in Kazakhstan, Uzbekistan, Kirghizia, and Tajikistan. This risk is the approximate estimate<br />
of risk for Amydarya and Syrdarya Rivers Basins.<br />
3. It is proposed the methodical approach to the analysis of risk dynamics (dose dynamic) for the talling piles accidents.<br />
4. It is proposed theIt is proposed the analysis of the tailing piles remediati<strong>on</strong> to carry out in terms cost-benefit analysis as<br />
functi<strong>on</strong> of time<br />
3) PARAMETRIC STUDIES FOR NUCLEAR CRITICALITY SAFETY USING MICROSOFT EXCEL - 16404<br />
Michael Crouse, URS - Washingt<strong>on</strong> Divisi<strong>on</strong> (USA)<br />
An important piece of performing calculati<strong>on</strong>s for new or revised Nuclear Criticality Safety Evaluati<strong>on</strong>s often includes parametric<br />
studies <strong>on</strong> <strong>on</strong>e or more parameters of importance, e.g. mass or moderati<strong>on</strong> level. Multiple input files may be generated quickly<br />
for use in SCALE and potentially MCNP utilizing the Visual Basic for Applicati<strong>on</strong>s (VBA) that is embedded within the Microsoft<br />
Office — Excel program.<br />
4) PROCESSING AND CONDITIONNING OF RADIOACTIVE SLUDGE - 16417<br />
Olivier Lemaire, Bouygues C<strong>on</strong>structi<strong>on</strong> Services Nucléaires (France); Bertrand Lantes, EDF, (France);<br />
Christophe LENagard,Bouygues C<strong>on</strong>structi<strong>on</strong> Services Nucléaires (France)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> EDF nuclear plants in operati<strong>on</strong> include 58 pressurized water reactors, c<strong>on</strong>sisting of 34 units of 900 MWe, 20 of 1300<br />
MWe and 4 of 1450 MWe.<br />
In 2008, arisings of low and intermediate level waste, short live activity, packages amounted to 84.5 m3 /reactor. During the<br />
same year, the plants in operati<strong>on</strong> shipped 4,901m3 packs to the Aube repository centre, this volume included 108 m3 of c<strong>on</strong>crete<br />
c<strong>on</strong>tainers c<strong>on</strong>taining intermediate level activity sludge.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> annual gross sludge volume produced per reactor ranges between about 1 and 2 m3 . This type of waste was not predicted<br />
at the design stage of the reactors since it was assumed that the number of low porosity filtering steps in the water circuits would<br />
be sufficient to trap any particles in suspensi<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> presence of sludge was verified after a few years of operati<strong>on</strong> at the bottom of<br />
sumps or tanks. Furthermore, allowance was not then made for the slow erosi<strong>on</strong> of the c<strong>on</strong>crete sumps nor for the fact that the tanks<br />
collecting waste overflow could behave as chemical reactor enhancing co-precipitati<strong>on</strong> phenomena.<br />
EDF finalized in the eighties a sludge cementati<strong>on</strong> process similar to the <strong>on</strong>e utilised for c<strong>on</strong>diti<strong>on</strong>ing evaporator c<strong>on</strong>centrates<br />
within c<strong>on</strong>crete c<strong>on</strong>tainers (processing of boric overflow). All the plants, according to their number of reactors, are equipped with<br />
<strong>on</strong>e or more facilities for waste encapsulati<strong>on</strong> within a cementati<strong>on</strong> matrix, but <strong>on</strong>ly the 900 MWe plants are able to c<strong>on</strong>diti<strong>on</strong> both<br />
evaporator c<strong>on</strong>centrates and sludge.<br />
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