Architecture and management of a geological repository - Andra

3 – High Level Long-Lived WasteA fifth subset of packages consists of solid waste and sludge that will be conditioned in the futureCEDRA and AGATE facilities of the CEA. The hypothesis currently adopted is conditioning of thewaste in CBF-C'2 fibre-reinforced containers. It is also supposed that mortar will be used toimmobilise the waste in the containers. As a precaution, the potential hydrogen production byradiolysis of water in the mortar is considered. Once again, these packages do not release radiation.A sixth subset of packages contains various technological waste, known as alpha waste, mainlycontaminated by plutonium during the manufacture of MOX fuels or reprocessing of spent fuels(especially for the conditioning of plutonium). The most representative waste, in terms of nature andflow, is waste from the manufacture of MOX fuels in the MELOX plant (Marcoule). This is composedof organic waste, filters and various predominantly metallic waste from glove boxes. The plannedconditioning process is compaction of the waste then transfer to standard compacted waste containers(CSD-C) in the ACC shop of the La Hague plant. The exact mixture of the waste mentioned above inthe packages depends on the hypotheses selected. The average weight of the finished packages is 635kilograms. As with other containers, the presence of organic matter in the packages means that theproduction of hydrogen by radiolysis of this matter must be considered. These packages do not releaseradiation.A seventh subset of packages contains pulverulent waste from the COGEMA plant at Marcoule. Thewaste comes either from the water filtration systems (ion-exchanger resins, zeolites, diatoms and poolsludge), or from mechanical processing of fuels (graphite). The planned conditioning method isembedding in a cement matrix and transfer to 428-litre stainless steel drums (EIP drums: see Figure3.2.9). The exact mixture of the waste mentioned above in the drums depends on the hypothesesselected. The average weight of the finished packages is 720 kilograms. Potential production ofhydrogen by radiolysis of the water in the matrix concrete must be taken into account. The equivalentß-γ dose rate in pseudo-contact (5 cm) with the packages is low at roughly 0.05 Sv/h.Figure 3.2.9EIP stainless steel drumAn eighth subset of packages, manufactured by the CEA, contain intermediate-level solidtechnological waste from shielded cells, mainly contaminated with ß-γ emitters. The waste isconditioned in compacted form in 500-litre steel containers (see Figure 3.2.10). It should be noted thatchanges have been made since the packages were first produced, concerning (i) the conditioningmatrix used to immobilise the waste in the containers: intially a cement-bitumen matrix, then from1990 a cementitious material, (ii) the material used for the container: the non-alloy steel used initiallywas replaced by stainless steel from 1994.DOSSIER 2005 ARGILE -ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL DISPOSAL SYSTEM83/495