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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Abstracts Sessi<strong>on</strong> 38<br />
3) HYDROGEOLOGIC MODELLING IN SUPPORT OF A PROPOSED DEEP GEOLOGIC REPOSITORY IN<br />
CANADA FOR LOW AND INTERMEDIATE LEVEL RADIOACTIVE WASTE - 16264<br />
J<strong>on</strong>athan Sykes, Stefano Normani, Y<strong>on</strong>g Yin, University of Waterloo (Canada);<br />
Eric Sykes, Mark Jensen, Nuclear Waste Management Organizati<strong>on</strong> (Canada)<br />
A Deep Geologic Repository (DGR) for Low and Intermediate Level radioactive waste has been proposed by Ontario Power<br />
Generati<strong>on</strong> for the Bruce Nuclear Power Development site in Ontario, Canada. <str<strong>on</strong>g>The</str<strong>on</strong>g> DGR is to be c<strong>on</strong>structed at a depth of about<br />
680 m below ground surface within the argillaceous Ordovician limest<strong>on</strong>e of the Cobourg Formati<strong>on</strong>. This paper describes a regi<strong>on</strong>al-scale<br />
geologic c<strong>on</strong>ceptual model for the DGR site and analyzes flow system evoluti<strong>on</strong> using the FRAC3DVS-OPG flow and<br />
transport model. This provides a framework for the assembly and integrati<strong>on</strong> of site-specific geoscientific data that explains and<br />
illustrates the factors that influence the predicted l<strong>on</strong>g-term performance of the geosphere barrier. In the geologic framework of the<br />
Province of Ontario, the Bruce DGR is located at the eastern edge of the Michigan Basin. Borehole logs covering Southern Ontario<br />
combined with site specific data have been used to define the structural c<strong>on</strong>tours at the regi<strong>on</strong>al and site scale of the 31 sedimentary<br />
strata that may be present above the Precambrian crystalline basement rock. <str<strong>on</strong>g>The</str<strong>on</strong>g> regi<strong>on</strong>al-scale domain encompasses an 18,500<br />
km2 regi<strong>on</strong> extending from Lake Hur<strong>on</strong> to Georgian Bay. <str<strong>on</strong>g>The</str<strong>on</strong>g> groundwater z<strong>on</strong>e below the Dev<strong>on</strong>ian is characterized by units c<strong>on</strong>taining<br />
stagnant water having high c<strong>on</strong>centrati<strong>on</strong>s of total dissolved solids that can exceed 300 g/l. <str<strong>on</strong>g>The</str<strong>on</strong>g> computati<strong>on</strong>al sequence<br />
involves the calculati<strong>on</strong> of steady-state density independent flow that is used as the initial c<strong>on</strong>diti<strong>on</strong> for the determinati<strong>on</strong> of pseudo-equilibrium<br />
for a density dependent flow system that has an initial TDS distributi<strong>on</strong> developed from observed data. L<strong>on</strong>g-term<br />
simulati<strong>on</strong>s that c<strong>on</strong>sider future glaciati<strong>on</strong> scenarios include the impact of ice thickness and permafrost. <str<strong>on</strong>g>The</str<strong>on</strong>g> selecti<strong>on</strong> of the performance<br />
measure used to evaluate a groundwater system is important. <str<strong>on</strong>g>The</str<strong>on</strong>g> traditi<strong>on</strong>al metric of average water particle travel time<br />
is inappropriate for geologic units such as the Ordovician where solute transport is diffusi<strong>on</strong> dominant. <str<strong>on</strong>g>The</str<strong>on</strong>g> use of life expectancy<br />
and groundwater age is a more appropriate metric for such a system. <str<strong>on</strong>g>The</str<strong>on</strong>g> mean life expectancy for the DGR and base case parameters<br />
has been estimated to be in excess of 8 milli<strong>on</strong> years.<br />
4) I-GRAPHITE WASTE MANAGEMENT IN FRANCE - 16301<br />
Odile Ozanam, Gerald Ouzounian, ANDRA (France)<br />
In France about 23,000 t<strong>on</strong>s of irradiated graphite waste were generated mainly from 9 nuclear gas-cooled reactors (UNGG<br />
type). All these reactors are now shut down. In France, a final disposal route has been decided for i-graphite waste management by<br />
the French Parliament in 2006. <str<strong>on</strong>g>The</str<strong>on</strong>g> planning act of June 28, 2006 has provisi<strong>on</strong>ed that a research and investigati<strong>on</strong> programme shall<br />
be established with a view to developing disposal opti<strong>on</strong>s for graphite waste.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> low specific activity of these wastes means shallow disposal facilities located in a geological layer with a low permeability.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> main radi<strong>on</strong>uclides that need specific attenti<strong>on</strong> for the l<strong>on</strong>g term safety are Chlorine 36 and Carb<strong>on</strong> 14. This establishes the<br />
main requirements for the graphite disposal. According to these requirements, underground disposal in a clay layer, at shallow<br />
depth, offers good performance in terms of the delay and the reducti<strong>on</strong> of the radi<strong>on</strong>uclide release; it also offers guarantees for the<br />
cover’s hydrodynamic and transport properties.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> progress of the programme makes it now necessary for a site to be found. Based <strong>on</strong> a bibliographical study, a wide-spread<br />
call for applicati<strong>on</strong>s took place during the sec<strong>on</strong>d semester of 2008.<br />
5) INDUSTRIAL COMPLEX FOR SOLID RADWASTE MANAGEMENT (ICSRM) AT CHERNOBYL NUCLEAR<br />
POWER PLANT FUNCTIONALITY OF THE FACILITIES - EXPERIENCE OF PROJECT EXECUTION - 16057<br />
Heiko Eichhorn, NUKEM Technologies GmbH (Germany)<br />
After an internati<strong>on</strong>al tendering process NUKEM was awarded to build the Industrial Complex for Solid Radwaste Management<br />
(ICSRM) at the Chernobyl Nuclear Power Plant. <str<strong>on</strong>g>The</str<strong>on</strong>g> ICSRM c<strong>on</strong>sists of four facilities (LOT): Lot 0: SLWS (Solid and Liquid<br />
Waste Storage) It is an interim storage facility for intermediate and high level l<strong>on</strong>g-lived radioactive waste in an existing building<br />
at ChNPP site. This building has been refurbished and modified to accommodate the required equipment. LOT 0 was handed<br />
over to the Employer June 2007 LOT 1: A solid waste retrieval facility, comprising the installati<strong>on</strong> of a retrieval facility for operati<strong>on</strong>al<br />
Low and Intermediate Level Short-Lived Waste (LILW-LL/SL) and High Level Waste (HLW) currently stored in the existing<br />
storage silo. Due to the Chernobyl accident, this storage also c<strong>on</strong>tains an unknown percentage of L<strong>on</strong>g-Lived (LL) waste. LOT<br />
1 was handed over to the Employer in April 2009. LOT 2: solid waste processing plant, comprising a plant for the sorting and segregati<strong>on</strong><br />
of all categories of solid radwaste and the processing of the solid LILW-LL/SL generated from the previous retrieval activities<br />
(LOT 1) and from the routine operati<strong>on</strong>al and decommissi<strong>on</strong>ing activities of the ChNPP. LILW-SL will be packaged and immobilized<br />
for removal to the near surface disposal facility (LOT 3) whilst higher category wastes (LILW-LL and HLW) will be packaged,<br />
over-packed and stored in a temporary storage facility (SLWS) while awaiting the c<strong>on</strong>structi<strong>on</strong> of an interim storage facility.<br />
LOT 2 is handed over to the Employer in April 2009. LOT 3: repository for the disposal of short-lived waste, comprising a near<br />
surface repository in accordance with the requirements of the Ukrainian Nuclear Regulatory Authorities and in the form of an engineered<br />
facility for the final disposal of LILW-SL c<strong>on</strong>diti<strong>on</strong>ed in LOT 2 and for wastes from the Liquid Radwaste Treatment Plant<br />
(LRTP) currently being build <strong>on</strong> Chernobyl NPP site. <str<strong>on</strong>g>The</str<strong>on</strong>g> facility will maintain its integrity during 300-year instuti<strong>on</strong>al c<strong>on</strong>trol period.<br />
LOT 3 was handed over to the Employer in December 2007.<br />
6) EXPERIENCES RELATED TO THE DEVELOPMENT OF A HIGH VOLUME VERY LOW LEVEL WASTE<br />
DISPOSAL FACILITY IN THE UK - 16371<br />
Andy Baker, Andy Baker C<strong>on</strong>sulting Ltd (UK); Andrea Borwick,WRG (UK); KayLin Loveland, Adam Meehan,<br />
Mike Travis, EnergySoluti<strong>on</strong>s (UK); Ian Warner, Magnox North Ltd (UK)<br />
New Government policy regarding waste disposal suggests that a wider range of opti<strong>on</strong>s should be evaluated for the management<br />
of low-level waste (LLW), including disposal to landfill. A new sub-category was created for nuclear industry waste disposal:<br />
high-volume very low level waste (HV VLLW). <str<strong>on</strong>g>The</str<strong>on</strong>g> Government has stated that it expects the majority of waste in this category<br />
that could go to landfill would c<strong>on</strong>sist of rubble and soil from decommissi<strong>on</strong>ing activities. This category would c<strong>on</strong>tain <strong>on</strong>ly<br />
small amounts of radioactivity and can be safely disposed to landfill, subject to appropriate c<strong>on</strong>trols.<br />
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