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Architecture and management of a geological repository - Andra

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3 – High Level Long-Lived WasteThe conditioned waste comprises various materials (metals, organic matter, glass, debris, etc.) mixedin the same package. The average weight <strong>of</strong> the finished packages varies between 1.6 <strong>and</strong> 2.3 metrictons, depending on the content (compacted or non-compacted, conditioning with overdrums). Giventhe chemical content <strong>of</strong> the packages, once again potential production <strong>of</strong> hydrogen by radiolysis <strong>of</strong> theorganic matter <strong>and</strong> conditioning matrix water must be considered. These packages do not releaseradiation.The main characteristics <strong>of</strong> the nine subsets <strong>of</strong> cemented or compacted technological waste packagesare summarised in Table 3.2.1.Table 3.2.1Summary <strong>of</strong> the main characteristics <strong>of</strong> subsets <strong>of</strong> cemented or compactedtechnological waste packagesPackagesubsetOverall volume <strong>of</strong> thepackage (m 3 )ContainermaterialEmbedding orimmobilising matrixPresence <strong>of</strong>metallicmaterialsPresence <strong>of</strong>organicmatter1 1 Concrete Cement-bitumen None x2 1.2 Fibre-reinforcedconcrete orasbestos cementCement x x3 1.8Concrete or nonalloyCement-bitumen or xx3.2 or 3.8 with overdrumsteelmortar4 0.5 Concrete Cement None x5 1.2 Fibre-reinforced Mortar x xconcrete6 0.18 Stainless steel None x x7 0.428 Stainless steel Cement None x8 0.5 Non-alloy or Cement-bitumen or xxstainless steel cementitious material9 1.22 Non-alloy steel Cement-bitumen orcementitious materialxx3.2.1.4 Cemented or compacted cladding wasteThis type <strong>of</strong> waste comes from spent fuel reprocessing in the COGEMA plants; it relates to themetallic framework components in the fuel assemblies. This waste is separated from recyclablenuclear materials (uranium, plutonium) <strong>and</strong> from fission products <strong>and</strong> minor actinides whenreprocessing commences during fuel shearing <strong>and</strong> dissolution operations.This waste is commonly known as "hulls <strong>and</strong> end caps" in pressurised water reactor fuel assemblies.The hulls are the cladding from the fuel rods, recovered in lengths <strong>of</strong> around three centimetres long,from which the nuclear material has been extracted by being dissolved in acid. The end caps are theparts located at both ends <strong>of</strong> the fuel assembly.The cladding waste under consideration here has come from reprocessing operations in the COGEMAplants at La Hague. They include (i) waste produced during previous reprocessing operations <strong>of</strong>NUGG <strong>and</strong> PWR fuels, today stored in silos <strong>and</strong> pits, <strong>and</strong> (ii) waste from current <strong>and</strong> futurereprocessing operations <strong>of</strong> the various types <strong>of</strong> PWR UOX <strong>and</strong> MOX fuels, defined in the designscenarios given in Section 3.1.There are several types <strong>of</strong> materials in cladding waste: magnesium-zirconium <strong>and</strong> magnesiummanganesealloys for the NUGG fuels; zirconium-tin (zircaloy 4) or zirconium-niobium (M5 alloy)alloys, stainless steels <strong>and</strong> nickel alloy for the PWR fuels. Following the conditioning hypothesesindicated below, some packages also contain technological waste formed <strong>of</strong> metal only (non-alloy <strong>and</strong>stainless steels) or a metallic-organic mixture. The mass <strong>of</strong> this technological waste represents aroundten per cent <strong>of</strong> the total mass <strong>of</strong> conditioned waste per package.DOSSIER 2005 ARGILE -ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL DISPOSAL SYSTEM85/495

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