Oxidation in air/steam mixtures of pre-oxidized Zircaloy-4 in the 750 - 950°C temperature range: experimental data and modeling for ASTECcode application

Autor: Gestin, Mathilde, Coindreau, Olivia, Pijolat , Michèle, Favergeon, Loïc, Duriez, Christian
Přispěvatelé: Département Procédés de Transformations des Solides et Instrumentation (PTSI-ENSMSE), Centre Sciences des Processus Industriels et Naturels (SPIN-ENSMSE), École des Mines de Saint-Étienne (Mines Saint-Étienne MSE), Institut Mines-Télécom [Paris] (IMT)-Institut Mines-Télécom [Paris] (IMT)-École des Mines de Saint-Étienne (Mines Saint-Étienne MSE), Institut Mines-Télécom [Paris] (IMT)-Institut Mines-Télécom [Paris] (IMT), Laboratoire Georges Friedel (LGF-ENSMSE), Université de Lyon-Centre National de la Recherche Scientifique (CNRS)-École des Mines de Saint-Étienne (Mines Saint-Étienne MSE), Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Institut Mines-Télécom [Paris] (IMT), ENS, American Nuclear Society, Atomic Energy Society of Japan, Korean Nuclear Society, Institut de Radioprotection et de Sûreté Nucléaire, PSN-RES
Jazyk: angličtina
Rok vydání: 2018
Předmět:
Zdroj: TOPFUEL 2018
TOPFUEL 2018, ENS; American Nuclear Society; Atomic Energy Society of Japan; Korean Nuclear Society, Sep 2018, Prague, Czech Republic
Popis: International audience; Spent fuel pools (SFPs) are large structures equipped with storage racks designed to temporarily store irradiated nuclear fuel removed from the reactor. In case of prolonged loss of cooling conditions or in case of a loss of coolant accident, the pool water may drop below the top of the spent fuel assemblies. The uncovered part of the fuel would be exposed to a steam/air mixture and the exothermal oxidation process of the cladding would result in a fast degradation of the fuel assembly and to the release of fission products.
Databáze: OpenAIRE