Tome Architecture and management of a geological repository - Andra
Tome Architecture and management of a geological repository - Andra
Tome Architecture and management of a geological repository - Andra
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7 - Spent fuel <strong>repository</strong> zoneSpent fuel is not considered for the time being as waste. Nevertheless an examination <strong>of</strong> its potentialdisposal in a deep <strong>geological</strong> formation <strong>repository</strong> has been made on the basis <strong>of</strong> scenarios formulatedfrom hypotheses on the back-end <strong>management</strong> <strong>of</strong> the nuclear energy cycle (cf. § 2).This examination is based on the characteristics <strong>and</strong> properties <strong>of</strong> the fuel produced by the PWRnuclear power plants, reactor systems now shut down, research reactors (UNGG, EL4) <strong>and</strong> FrenchNational Defence activities <strong>and</strong> included the safety functions that must be ensured for their disposal.This chapter describes the design for the spent fuel <strong>repository</strong> zone. It states how designs adoptedabroad in the granite medium can be transposed to the French context to fulfil the safety functionsdefined in chapter 3.1.The proposed cell design <strong>and</strong> <strong>repository</strong> zone architecture options are also based on the optionsalready envisaged for the disposal <strong>of</strong> vitrified C waste.Finally this chapter describes how these options can be implemented for a reversible disposal process<strong>and</strong> meet operational safety <strong>and</strong> security requirements.7.1 Spent fuel assemblies7.1.1 The different types <strong>of</strong> spent fuelAs in the case <strong>of</strong> B <strong>and</strong> C waste, the spent fuel inventory has been organised by type (cf. § 2.3).This organisation is based on a tree structure that groups together fuel assemblies with similar thermal<strong>and</strong> radiological characteristics on one level, <strong>and</strong> then the assembly families differentiated by origin.Table 7.1.1Spent fuel reference packages <strong>and</strong> assembly familiesAssembly families included in the reference packages <strong>and</strong> referenceReference fuelsub-packagesLev. 1 Lev. 2 Lev. 3 Description DescriptionCU1CU2CU3PWR, UOX <strong>and</strong> enriched uranium fuelPWR <strong>and</strong> MOX fuelCU3.1UNGG <strong>and</strong> EL4 fuelCU3.2CELESTIN fuelCU3.3 Nuclear propulsion fuel Batch A7.1.1.17.1.1.27.1.1.1 PWR fuel assembliesThe reference fuel assembly corresponds to a second-generation advanced assembly designed byFRAGEMA with thicker guide thimbles <strong>and</strong> zirconium alloy cladding. It is illustrated in Figure 7.1.1.It is called AFA-2GE for the PWR 900 MWe reactors <strong>and</strong> AFA-2LE for the PWR 1300 MWe <strong>and</strong>1450 MWe reactors.Dossier 2005 granite - ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL REPOSITORY194/228
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