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Tome Architecture and management of a geological repository - Andra

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6 – C waste <strong>repository</strong> zoneFigure 6.1.2PIVER containersThese are low-capacity packages (39 or 45 litres depending on the type <strong>of</strong> container) containing glassweighing between 20 <strong>and</strong> 120 kilograms. An average weight <strong>of</strong> 72 kilograms <strong>of</strong> vitrified waste perpackage has been adopted for the study, with a total average weight <strong>of</strong> 90 kilograms for a full package(vitrified waste + container).The radiological activity <strong>of</strong> the packages has decreased considerably given their date <strong>of</strong> production. Itcontinues to be dominated by two medium-life fission products - strontium-90 ( 90 Sr) <strong>and</strong> caesium-137( 137 Cs). These generate residual thermal release, currently on the order <strong>of</strong> about thirty watts perpackage. The equivalent β-γ dose rate in pseudo-contact (5 cm) with the package is around 70 Sv/h,becoming around 45 Sv/h by 2025.The UMo glass waste packages correspond to future conditioning <strong>of</strong> solutions <strong>of</strong> existing fissionproducts; these are produced by UNGG fuels recovered in the COGEMA UP2-400 plant at La Hague.The chemical nature <strong>of</strong> the solutions requires a specific glass to be formulated <strong>and</strong> modifications toprocess equipment, particularly the vitrification furnace. Following the hypotheses adopted, theaverage weight <strong>of</strong> the conditioned waste is 400 kilograms per package. Strontium-90 <strong>and</strong> caesium-137also play an important role here in the radiological activity <strong>of</strong> the packages, although this hasdecreased tremendously given the age <strong>of</strong> the solutions. Subsequently, the residual thermal release iscurrently around 70 watts per package. The equivalent β-γ dose rate in pseudo-contact (5 cm) with thepackage is around 15 Sv/h, becoming around 10 Sv/h by 2025.This waste will be conditioned in a stainless steel container identical to the one used today in theCOGEMA R7 <strong>and</strong> T7 vitrification shops at La Hague. This container, known as the St<strong>and</strong>ard VitrifiedWaste Container (CSD-V), is presented in Figure 6.1.3.Dossier 2005 granite - ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL REPOSITORY161/228

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