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
2 – High-Level <strong>and</strong> Long-Lived wasteResearch carried out at the CEA, especially on behalf <strong>of</strong> the French nuclear power programme, <strong>and</strong> theroutine operation <strong>and</strong> maintenance <strong>of</strong> its facilities, are other sectors that have produced a wide range <strong>of</strong>waste. Most <strong>of</strong> this waste, made up <strong>of</strong> intermediate-level solid <strong>and</strong> liquid effluent waste, has beenconditioned using immobilisation materials <strong>and</strong> packages <strong>of</strong> various types <strong>and</strong> geometry.Finally, activities linked to national defence produce intermediate-level technological waste.For the <strong>repository</strong> studies, the package inventory (in terms <strong>of</strong> type <strong>and</strong> quantity) includes all wastealready produced as well as waste that may be produced through operating existing nuclear facilities.With regard to future production, this implies the need to formulate waste production <strong>and</strong> conditioninghypotheses, especially concerning <strong>management</strong> <strong>of</strong> nuclear power plants fleet.Currently 58 pressurised water reactors, commissioned between 1977 <strong>and</strong> 1999, are operated toproduce electricity. The tonnage <strong>of</strong> nuclear fuels removed from these reactors over their totaloperating period is estimated at 45,000 metric tons <strong>of</strong> heavy metal (tHM). This estimation is based ona combination <strong>of</strong> hypotheses concerning (i) the average lifetime <strong>of</strong> units (forty years), (ii) powerproduction (16,000 terawatt-hours total production), (iii) the gradual increase <strong>of</strong> nuclear fuel "burn-up"in the reactors 1 .The fuel types considered <strong>and</strong> the corresponding average fuel burn-up is as follows:- three generations <strong>of</strong> uranium oxide fuels: UOX1, UOX2, UOX3, irradiated respectively at33 gigawatt-days per metric ton <strong>of</strong> fuel (GWd/t), 45 GWd/t <strong>and</strong> 55 GWd/t, on average;- fuels containing recycled uranium (URE) irradiated on average at 45 GWd/t;- mixed uranium oxide <strong>and</strong> recycled plutonium oxide fuels (MOX) irradiated at 48 GWd/t onaverage.On this basis, four nuclear fuel <strong>management</strong> scenarios were selected for the studies. The principlebehind these scenarios is to include various possible industrial strategies without singling out any <strong>of</strong>them. This process makes it possible to consider a very wide range <strong>of</strong> waste types <strong>and</strong> examine thetechnical aspects <strong>of</strong> the various packages.The first three scenarios, designated as S1a, S1b <strong>and</strong> S1c, correspond to an ongoing reprocessing <strong>of</strong>spent fuel removed from EDF reactors. Scenario S1a supposes that all these fuels (UOX, URE <strong>and</strong>MOX) are reprocessed. This scenario includes the hypothesis <strong>of</strong> incorporating fission productmixtures <strong>and</strong> minor actinides from UOX <strong>and</strong> MOX fuels in glass. Also, for study purposes, it isassumed that a very small part <strong>of</strong> the plutonium from reprocessed UOX fuels is incorporated in somepackages. This scenario therefore covers a variety <strong>of</strong> vitrified C package typologies.In scenarios S1b <strong>and</strong> S1c, MOX fuels are not reprocessed, allowing the hypothesis <strong>of</strong> their directdisposal to be explored.Scenarios S1b <strong>and</strong> S1c have been separated in order to study, in scenario S1b, the possibility <strong>of</strong>increasing the waste concentration in glass, compared with the packages currently produced; thisgreater concentration would result in a slightly greater release <strong>of</strong> heat from the packages.Finally, a fourth scenario, designated as S2, which supposes that reprocessing is stopped, is used forthe exploratory study <strong>of</strong> direct disposal <strong>of</strong> UOX <strong>and</strong> URE fuels, as well as the MOX fuels consideredin scenarios S1b <strong>and</strong> S1c. In this scenario the fuels are considered to be waste, which, we shouldrecall, is not the present case.To be able to estimate the quantity <strong>of</strong> waste produced, scenarios S1a, S1b <strong>and</strong> S1c are based on thefollowing distribution <strong>of</strong> various types <strong>of</strong> fuels removed from existing reactors: 8,000 tHM <strong>of</strong> UOX1(33 GWd/t), 20,500 tHM <strong>of</strong> UOX2 (45 GWd/t), 13,000 tHM <strong>of</strong> UOX3 (55 GWd/t), 800 tHM <strong>of</strong> URE(45 GWd/t) <strong>and</strong> 2,700 tHM <strong>of</strong> MOX (48 GWd/t). In scenarios S1b <strong>and</strong> S1c, the direct disposal studyconcerns all the 2,700 tHM <strong>of</strong> spent MOX fuels.1The burn-up <strong>of</strong> a nuclear fuel assembly expresses the energy produced in the reactor by the fissile material that it contains (uraniumoxide or mixture <strong>of</strong> uranium <strong>and</strong> plutonium oxides)Dossier 2005 Granite - ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL REPOSITORY21/228
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