Architecture and management of a geological repository - Andra

3 – High Level Long-Lived WasteQuantitative data relating to PWR fuels are found in Table 3.3.6.Table 3.3.6Number of PWR fuel assemblies"Short" UOX AFA-2GEassembly, type CU1"Long" UOX AFA-2LEassembly, type CU1Production sitesEDFScenarioS1aNumber of PWR fuel assembliesScenario ScenarioS1b S1cScenarioS20 0 0 27 2000 0 0 26 800Total UOX assemblies, type CU1 0 0 0 54 000"Short" MOX AFA-2GEassembly, type CU2EDF 0 5 400 5 400 4 000Total MOX assemblies, type CU2 0 5 400 5 400 4 000Furthermore, 5,810 primary claddings are to be considered for type CU3 fuels, if appropriate.3.4 Primary waste package reception flux hypothesisTo study operating resources in a potential repository, and the drifts and access shafts, flowhypotheses for packages received on a repository site have been established, consistent with the totalnumbers of packages listed.As a reference, an annual reception rate of 5,000 primary waste packages has been envisaged for Bwaste. This corresponds to emplacement of the waste packages inventory into the repository over aforty-year period. With the exception of some packages produced late, particularly the B1 referencepackage, note that all or the vast majority of the other reference packages will already have beenproduced by 2020.Chronologically, the C0 reference packages will be the first vitrified C waste packages availabletechnically for repository disposal in view of their heat rating. 400 packages per year is the rateadopted for the hypothesis, corresponding to a resorption of storage facilities over ten years or so.It is assumed that the other vitrified C waste packages (C1, C2, C3 and C4 in scenario S1a, C1 and C2in scenarios S1b and S2, C1 only in scenario S1c) will be stored temporarily before final disposal, toallow their heat rating to decrease. The studies presented in Chapter 5 suggest a reasonable temporarystorage period of 60 to 70 years under the concepts studied and heat transfer criteria currently beingconsidered.In any event, the hypothesis of an annual reception rate of 600 C1 to C4 reference packages (700packages per year for C1 reference packages under scenario S1c) will permit resorption of storagefacilities at a rate allowing for the packages contained therein to show a consistent heat rating, giventhe decrease in radioactivity. This corresponds to a resorption of storage facilities over about fiftyyears.CU2 fuels identified in scenarios S1b, S1c and S2 will be received as appropriate after a currentlyestimatedtemporary storage period of at least 90 years, at an annual rate of 150 assemblies. Theirresorption will take place over about forty years under scenarios S1b and S1c (or thirty for scenarioS2). Lastly, for CU1 fuels (scenario S1), the study considers the hypothesis of 1,650 assemblies peryear.Note that an annual reception rate of 400 primary claddings can be envisaged for CU3 fuels,corresponding to a resorption of storage facilities over about fifteen years.DOSSIER 2005 ARGILE -ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL DISPOSAL SYSTEM104/495