HT cladding oxidation in SFP-LOCA conditions examined with microRaman imaging and 18O tracer techniques

Autor: MERMOUX, Michel, IDARRAGA, Isabel, Guerain, Mathieu, Kasperski, Anne, GESTIN, Mathilde, Duriez, Christian

Publikováno v: 25th International QUENCH Workshop, QUENCH
25th International QUENCH Workshop, QUENCH, Oct 2019, KARLSRUHE, Germany

International audience; Zircaloy-4 high temperature oxidation has been studied in mixed O2 + N2 + steam atmospheres and at temperatures in the 700-950°C range, conditions relevant to Spent Fuel Pool Loss-of-Coolant or Loss-of-Cooling (SFP-LOCA) scen

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::5b4ecd889b8e02825f611956dab7c4f3
https://hal.archives-ouvertes.fr/hal-02982045

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

Publikováno v: TOPFUEL 2018
TOPFUEL 2018, ENS; American Nuclear Society; Atomic Energy Society of Japan; Korean Nuclear Society, Sep 2018, Prague, Czech Republic

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 c

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::967557f88f9f7195b66d58316f874b56
https://hal.archives-ouvertes.fr/hal-02134247

Study on high temperature oxidation of Zircaloy-4 in air and steam

Autor: Gestin, Mathilde, Coindreau, Olivia, Pijolat , Michèle, Duriez, Christian, Peres, Véronique

Publikováno v: High Temperature Corrosion-Gordon Research Conference (GRC)-Gordon Research Seminar (GRS)
Christine Geers; Juho Lehmusto. High Temperature Corrosion-Gordon Research Conference (GRC)-Gordon Research Seminar (GRS), Jul 2017, New-London, United States

International audience; Zircaloy-4 (Zy-4) cladding, the first containment of UO2 fuel in Pressurized Water Reactors, could be exposed to air and steam in case of spent fuel pool accidents. A complete kinetic study is conducted; temperature jumps or g

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::fe26e4072312a0decf7e7c7be8177352
https://hal.archives-ouvertes.fr/hal-01720824/document