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Tome Architecture and management of a geological repository - Andra

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2 – High-Level <strong>and</strong> Long-Lived wasteThis chapter describes the primary HLLL waste packages that are considered for the <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 fuel consistent with current industrial practice,reprocessing <strong>of</strong> URE <strong>and</strong> MOX fuel, possible increase in the heat rating <strong>of</strong> vitrified C waste <strong>and</strong> theexploratory hypothesis <strong>of</strong> direct disposal <strong>of</strong> UOX, URE <strong>and</strong> MOX fuel.This chapter then presents the two categories <strong>of</strong> waste that fall into the framework <strong>of</strong> the30 December 1991 Act. It also provides an inventory model [3] which forms the basis for constructingall the design <strong>and</strong> dimensioning studies for the <strong>repository</strong>. The model brings together all the variouswaste families by defining waste “reference packages” (or package types) covering each a more or lessimportant range, varying in extent, <strong>of</strong> primary waste packages. The notion <strong>of</strong> waste reference packageis an essential element structuring the technical options considered in response to the diversity <strong>of</strong>primary waste. It is therefore a key to reading the following chapters. The inventory model stipulateswhich hypotheses are adopted for the number <strong>of</strong> primary packages to be incorporated for each studyscenario.2.1 The production <strong>of</strong> HLLL waste, study scenariosThe activity sectors producing the greatest volume <strong>of</strong> HLLL waste come within the nuclear powerindustry (EDF electricity-generating reactors, COGEMA fuel reprocessing plants, MELOX plantproducing MOX fuel) 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 “PWR” pressurised water reactors (58 <strong>of</strong> these are currentlyoperated) are reprocessed in the La Hague plants, except for URE <strong>and</strong> MOX fuels, prepared fromreprocessed uranium <strong>and</strong> plutonium respectively, which at present are stored in pools [4].Reprocessing operations produce various types <strong>of</strong> waste, either directly resulting from spent fuel(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 equipments) or radioactive effluent treatment (sludge). Currently, waste is conditioned in-line inthe 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> the so-called “UMo”solutions currently stored at La Hague, it should be noted that all fission product solutions, as well aseffluent sludges 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 mainly concerns neutronic poison <strong>and</strong> control rod assemblies <strong>and</strong>, to a lesser extent, waste suchas source clusters <strong>and</strong> metal parts (thimbles <strong>and</strong> pins for example). All waste currently produced isstored in pools close to the reactors.Dossier 2005 Granite - ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL REPOSITORY20/228

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