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Communication Dans Un Congrès Année : 2015

A reverse method for the determination of the radiological inventory of irradiated graphite at reactor scale

Résumé

About 17,000 tons of irradiated graphite waste will be produced from the decommissioning of the six gas-cooled nuclear reactors operated by Electricité De France company (EDF), a French energetic utility. Determining the radionuclide content of this waste is an important in order to determine the best suited management strategy. As evidenced by numerous studies nuclear graphite is a very pure material, however, it cannot be considered from an analytical viewpoint as a usual homogeneous material. Because of graphite high purity, radionuclide measurements in irradiated graphite exhibit very high discrepancies especially when corresponding to precursors at trace level. Therefore the assessment of a radionuclide inventory only based on few number of radiochemical measurements leads in most of cases to a gross over or under-estimation of radionuclide inventory. A reverse method using an identification calculation–measurement process is proposed by EDF in order to assess the radionuclide inventory as precisely as possible. A physical interpretation of the results is performed by Institut de Radioprotection et de Sureté Nucléaire (IRSN), and first elements of validation of the proposed reverse method are given in this paper.
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Dates et versions

hal-04258535 , version 1 (25-10-2023)

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Paternité - Pas d'utilisation commerciale - Pas de modification

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  • HAL Id : hal-04258535 , version 1

Citer

Gregory Nicaise, Bernard Poncet. A reverse method for the determination of the radiological inventory of irradiated graphite at reactor scale. EUROSAFE FORUM 2015, European Technical Safety Organisations Network, Nov 2015, Brussels (Belgium), Belgium. ⟨hal-04258535⟩

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