A reverse method for the determination of the radiological inventory of irradiated graphite at reactor scale
Résumé
Irradiated graphite waste will be produced from the decommis-sioning of the six gas-cooled nuclear reactors operated by Elec-tricité De France (EDF). Determining the radionuclide contentof this waste is an important legal commitment for both safetyreasons and in order to determine the best suited managementstrategy. As evidenced by numerous studies nuclear graphite isa very pure material, however, it cannot be considered froman analytical viewpoint as a usual homogeneous material. Be-cause of graphite high purity, radionuclide measurements in ir-radiated graphite exhibit very high discrepancies especiallywhen corresponding to precursors at trace level. Therefore theassessment of a radionuclide inventory only based on fewnumber of radiochemical measurements leads in most of casesto a gross over or under-estimation that can be detrimental tographite waste management. A reverse method using an identi-fication calculation–measurement process is proposed in orderto assess the radionuclide inventory as precisely as possible.
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Licence : CC BY - Paternité
Licence : CC BY - Paternité