Effect of a pre-oxide on the high temperature steam oxidation of Zircaloy-4 and M5Framatome alloys

Autor: Jean-Christophe Brachet, Antoine Ambard, M. Le Saux, Raphaël Chosson, Stéphane Urvoy, Elodie Rouesne, Valérie Vandenberghe

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2019, 518, pp.386-399. ⟨10.1016/j.jnucmat.2019.03.023⟩

International audience; The effect of a pre-existing oxide layer formed at low temperature on the subsequent oxidation in steam at high temperature was studied for Zircaloy-4 and M5 Framatome alloys. Various pre-oxidation conditions (air at 550 °C,

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d42f9b54c565cc198ba5adec32fdc516
https://doi.org/10.1016/j.jnucmat.2019.03.023

Evaluation of Equivalent Cladding Reacted parameters of Cr-coated claddings oxidized in steam at 1200 °C in relation with oxygen diffusion/partitioning and post-quench ductility

Autor: J. Bischoff, Jean-Christophe Brachet, Philippe Bossis, T. Vandenberghe, Edouard Pouillier, G. Nony, T. Guilbert, Hervé Palancher, M. Le Saux, Raphaël Chosson, A. Lequien, Stéphane Urvoy, C. Miton

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2020, 533, pp.152106-1-152106-16. ⟨10.1016/j.jnucmat.2020.152106⟩
Journal of Nuclear Materials, 2020, 533, pp.152106-1-152106-16. ⟨10.1016/j.jnucmat.2020.152106⟩

International audience; Cr-coated M5(Framatome) cladding materials are studied and developed within the CEA-Framatome-EDF French nuclear fuel joint program as Enhanced Accident Tolerant Fuel claddings for Light Water Reactors. The objective of this p

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c1d6034589f30c013d03d6b517dda5e4
https://hal.archives-ouvertes.fr/hal-02639341

Breakaway oxidation of zirconium alloys exposed to steam around 1000 °C

Autor: Valérie Vandenberghe, Matthieu Le Saux, Antoine Ambard, Raphaël Chosson, Jean-Christophe Brachet

Publikováno v: Corrosion Science
Corrosion Science, 2020, 176 (108936), pp.1-21. ⟨10.1016/j.corsci.2020.108936⟩
Corrosion Science, Elsevier, 2020, 176 (108936), pp.1-21. ⟨10.1016/j.corsci.2020.108936⟩

International audience; The breakaway oxidation of Zircaloy-4 and M5Framatome alloys oxidized in flowing steam around 1000 °C wasstudied. The influences of oxidation temperature between 950 and 1050 °C, one-side versus two-side oxidationand chemica

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::575f8991a2b31b9f16623059a6118504
https://doi.org/10.1016/j.corsci.2020.108936

Creep behavior at high temperature of the oxygen stabilized zirconium alpha phase of fuel cladding tubes oxidized in loca conditions

Autor: Raphaël Chosson, Vandenberghe, V., Gourgues-Lorenzon, A. -F, Crépin, J., Bracher, J. -C, Cabrera, A., Garat, V.

Publikováno v: HAL
LWR Fuel Performance Meeting / Top Fuel 2013
LWR Fuel Performance Meeting / Top Fuel 2013, Sep 2013, Charlotte, United States. pp.520-527
Scopus-Elsevier

International audience; During hypothetical Loss-Of-Coolant-Accident (LOCA) scenarii, zirconium alloy fuel cladding tubes are oxidized at high temperature (HT): zirconia and oxygen-stabilized alpha, called alpha(O) are formed on the outer surface of

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::e05c5877ec66791cb8a9a74c1113dba4
https://hal-mines-paristech.archives-ouvertes.fr/hal-01427453