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Architecture and management of a geological repository - Andra

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3 – High Level Long-Lived WasteThe other package characteristics (heat rating, equivalent dose rate, weight) are otherwise identical tothe first sub-assembly.The third package sub-assembly only contains cladding waste from PWR fuels reprocessed in the past<strong>and</strong> now stored. The packages weigh 725 kilograms on average. Given the age <strong>of</strong> the waste, thepackages do not transfer heat. Their irradiation level is around 5 Sv/h; it will be around 1 Sv/h by2025.The third package sub-assembly only contains cladding waste from NUGG fuels reprocessed in thepast <strong>and</strong> now stored. The finished packages weigh 350 kilograms on average. Given the age <strong>of</strong> thewaste, the packages do not transfer heat. Their irradiation level is also lower than for the previous subassemblies,namely around 0.4 Sv/h.Table 3.2.2 summarises the principal characteristics <strong>of</strong> the four sub-assemblies <strong>of</strong> compacted claddingwaste packages.Table 3.2.2Summary <strong>of</strong> principle characteristics <strong>of</strong> sub-assemblies <strong>of</strong> compacted claddingwaste packagesPackage subassemblyCladding wastematerials1 Zirconium-tin orzirconium-niobiumalloys, stainlesssteels, nickel alloy2 Ditto sub-assembly13 Zirconium-tin alloy,stainless steels,nickel alloy4 MagnesiumzirconiumormagnesiummanganesealloysPresence <strong>of</strong>technologicalwastePresence <strong>of</strong>organicmatter3.2.1.5 Cladding <strong>and</strong> technological waste placed in drumsProduction <strong>of</strong>gas byradiolysis(H 2 )Thermicity,irradiation levelwhen packagesproducedx x x Packages transferlittle heat, extremelyirradiatingx None None Packages transferlittle heat, extremelyirradiatingNone None None Packages do nottransfer heat,moderatelyirradiatingNone None None Packages do nottransfer heat, onlyslightly irradiatingThis groups waste produced on the COGEMA Marcoule site <strong>and</strong> currently stored, excluding bitumenwaste <strong>and</strong> cemented pulverulent waste described above. It includes (i) operating waste from theMarcoule vitrification shop, (ii) cladding waste from fuels reprocessed in the UP1 plant <strong>and</strong> (iii)operating <strong>and</strong> maintenance technological waste from the Marcoule site facilities.The waste is placed in stainless steel drums. Note that the modalities for limiting the residual voidsinside the primary packages have yet to be defined.A first package sub-assembly contains technological waste from operations in the Marcoulevitrification shop (AVM). The waste formed <strong>of</strong> equipment, tools <strong>and</strong> various steel parts is deposited ina stainless steel container <strong>of</strong> similar geometry to the AVM vitrified waste containers. The packagesweigh 160 kilograms on average <strong>and</strong> may weigh as much as 320 kilograms (excluding wasteimmobilisation material). Radiological activity corresponds to contamination <strong>of</strong> the waste surfacearea. These packages do not transfer heat <strong>and</strong> have an irradiation level <strong>of</strong> around 0.05 Sv/h.DOSSIER 2005 ARGILE -ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL DISPOSAL SYSTEM88/495

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