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Architecture and management of a geological repository - Andra

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3 – High Level Long-Lived WasteThis chapter describes the primary waste packages that are considered for the <strong>geological</strong> <strong>repository</strong>feasibility study. It draws particular attention to their diversity. It is based on the results <strong>of</strong> the workcarried out jointly between <strong>Andra</strong> <strong>and</strong> the producers concerning (i) surveying, <strong>and</strong> (ii) collecting <strong>and</strong>structuring the knowledge.Firstly it sets out the waste production scenarios underpinning the inventory considered. The survey <strong>of</strong>existing waste is based on knowledge <strong>of</strong> past <strong>and</strong> present processes, production reports for eachfacility, identification <strong>of</strong> storage sites <strong>and</strong> control <strong>of</strong> their contents. In considering future waste,hypotheses have been formulated concerning the continuation <strong>of</strong> production by the various facilities.For waste from nuclear power plants, several scenarios have been selected to cover the variouspossible situations: ongoing reprocessing <strong>of</strong> spent UOX fuels consistent with current industrialpractice, reprocessing <strong>of</strong> URE <strong>and</strong> MOX fuels, possible increase in the heat rating <strong>of</strong> vitrified C waste<strong>and</strong> the exploratory hypothesis <strong>of</strong> direct disposal <strong>of</strong> UOX, URE <strong>and</strong> MOX fuels.This chapter then sets out the primary waste package characteristics for each existing or plannedfamily surveyed, on the basis <strong>of</strong> the relevant knowledge collected by the producers.It also provides an inventory model [3] which forms the basis for constructing all the design <strong>and</strong>dimensioning studies for the <strong>repository</strong>. The model brings together all the various waste families bydefining "waste packages types" covering each a more or less important range, varying in extent, <strong>of</strong>primary waste packages. The notion <strong>of</strong> waste package types is an essential element structuring thetechnical options considered in response to the diversity <strong>of</strong> primary waste. It is therefore a key toreading the following chapters.Finally, the chapter sets out the hypotheses concerning waste disposal volumes over time for variousscenarios.3.1 Waste production: the study scenariosThe activity sectors producing the greatest volume <strong>of</strong> waste studied come within the nuclear powerindustry (EDF electricity-generating reactors, COGEMA fuel reprocessing plants, MELOX plantproducing MOX fuels) or research <strong>and</strong> national defence activities (CEA centres).The study must also consider waste produced upstream <strong>of</strong> the cycle, during uranium ore processingoperations, <strong>and</strong> end-<strong>of</strong>-life radioactive objects from various industrial <strong>and</strong> medical activities.Currently, spent fuels removed from pressurised water reactors (58 <strong>of</strong> these are currently operated) arereprocessed in the La Hague plants, except for URE <strong>and</strong> MOX fuels, prepared from reprocesseduranium <strong>and</strong> plutonium respectively, which at present are stored in pools [39].Reprocessing operations produce various types <strong>of</strong> waste, either directly resulting from spent fuels(fission product solutions <strong>and</strong> minor actinides, fuel assembly cladding waste), or linked to the use <strong>of</strong>facilities for maintenance operations (technological waste resulting from replacement <strong>of</strong> parts <strong>and</strong>other equipment) or radioactive effluent treatment (sludge). Currently, wastes are conditioned in-linein the UP2-800 <strong>and</strong> UP3 plants at La Hague. In previous-generation plants (UP2-400 at La Hague <strong>and</strong>UP1 at Marcoule, now shut down), where fuels from various reactor generations were reprocessed,especially the first-generation NUGG (Natural Uranium-Graphite-Gas), part <strong>of</strong> the waste was stored inunconditioned form in specific facilities. However, with the exception <strong>of</strong> Umo solutions currentlystored at La Hague (see Section 3.2.2.1), it should be noted that all fission product solutions, as well aseffluent sludge at Marcoule, have been conditioned.In addition, the operation <strong>of</strong> electricity-generating nuclear reactors requires systems for starting up <strong>and</strong>controlling the reactors. After a certain time these are replaced <strong>and</strong> become waste. This mainlyconcerns neutronic poison <strong>and</strong> control rod assemblies <strong>and</strong>, to a lesser extent, waste such as sourceclusters <strong>and</strong> metal parts (thimbles <strong>and</strong> pins for example). All waste currently produced is stored inpools close to the reactors.DOSSIER 2005 ARGILE -ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL DISPOSAL SYSTEM74/495

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