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Tome Architecture and management of a geological repository - Andra

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5 – B waste <strong>repository</strong> zoneproduced, taking the conditioning hypotheses set out below). Since this is largely due to cobalt, theresidual heat rating <strong>of</strong> the package drops rapidly as the cobalt decays. As an illustration, the heat ratingis divided by 2 after 5 years <strong>of</strong> cooling, by 3.5 after 10 years <strong>of</strong> cooling <strong>and</strong> by 6 after 15 years <strong>of</strong>cooling. Another consequence <strong>of</strong> this radiological inventory is the high level <strong>of</strong> radiation <strong>of</strong> thepackages. Thus, the equivalent ß-γ dose rate in pseudo-contact with the package (i.e. at a distance <strong>of</strong>5 centimetres) is roughly 50 sieverts per hour (Sv/h), at the time <strong>of</strong> its production. This is mainlyattributable to 60 Co, but also to silver-108m ( 108m Ag) whose half-life is 420 years, <strong>and</strong> remains at arelatively high level even after 10 years' cooling (around 15 Sv/h).The conditioning hypothesis considered in the study 22 is compaction <strong>of</strong> the waste placed in holders 23 , thentransfer to stainless steel containers known as "St<strong>and</strong>ard Compacted Waste Containers" (CSD-C) in smallformat (see Figure 5.1.2).Figure 5.1.2St<strong>and</strong>ard compacted waste containers (CSD-C)The conditioning hypothesis assumes a weight <strong>of</strong> 400 kilograms <strong>of</strong> waste per package, made up <strong>of</strong> amixture <strong>of</strong> different types <strong>of</strong> activated waste in the following proportions: 5% neutronic poison rods,78% control rods <strong>and</strong> 17% various metal wastes. The weight <strong>of</strong> the finished package is around510 kilograms.It should be noted that these packages contain no organic materials <strong>and</strong> are not liable to produce gas(hydrogen) by radiolysis.5.1.2 Bituminised liquid effluent processing sludgeThe second group <strong>of</strong> B wastes comes from radioactive liquid effluents resulting from the operation <strong>of</strong>fuel reprocessing facilities. The effluents considered here are generated at various stages <strong>of</strong> fuelreprocessing <strong>and</strong> during work carried out on equipment <strong>and</strong> facilities (decontamination, flushing).These effluents are collected in treatment stations where they are decontaminated by chemicalprocesses before discharge. The residual waste is then recovered in the form <strong>of</strong> sludge.In the “STEL” effluent treatment station at Marcoule <strong>and</strong> STE3 at La Hague, opened in 1966 <strong>and</strong> 1989respectively, this sludge has been conditioned by embedding in bitumen, which is then put in steeldrums. On the other h<strong>and</strong>, sludge from effluents produced <strong>and</strong> chemically treated at La Hague STE2(Effluent Treatment Station No. 2) from 1966 to 1990 have been gradually stored in tanks <strong>and</strong> silos atthe plant, awaiting conditioning. The planned conditioning method for these sludges is also embeddingin a bitumen matrix.2223An alternative conditioning mode, not dealt with here, is being studied at EDFLarge rods <strong>and</strong> CIS thimbles are cut into sections before being placed in compaction holdersDossier 2005 Granite - ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL REPOSITORY98/228

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