Influence of grain size on the high-temperature creep behaviour of M5Framatome1 zirconium alloy under vacuum

Autor: Gourgues-Lorenzon, Anne-Françoise, Trego, G., Brachet, J.C., Vandenberghe, V., Portier, L., Gélébart, L., Chosson, R., Soulacroix, J., Forest, S., Gourgues-Lorenzon, A.F.

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2022, 560, pp.153503. ⟨10.1016/j.jnucmat.2021.153503⟩

International audience

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::947598168324d0cc1ffb37786a56df28
https://doi.org/10.1016/j.jnucmat.2021.153503

Effect of a pre-oxide on the high temperature steam oxidation of Zircaloy-4 andM5 alloys

Autor: Lesaux, M., Brachet, Jc., Vandenberghe, V., Urvoy, S., Rouesne, E., Chosson, R., Ambard, A.

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2019, 518, pp.386-399. ⟨10.1016/j.jnucmat.2019.03.023⟩
Journal of Nuclear Materials, 2019, ⟨10.1016/j.jnucmat.2019.03.023⟩
Journal of Nuclear Materials, 2019, 518, pp.386-399. ⟨10.1016/j.jnucmat.2019.03.023⟩
Journal of Nuclear Materials, Elsevier, 2019, ⟨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=dedup_wf_001::88cb1df3e91b9746ac773185daa30717
https://hal-ensta-bretagne.archives-ouvertes.fr/hal-02149361

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Mechanical behavior at high temperature of highly oxygen- or hydrogen-enriched α and (prior-) $\beta$ phases of zirconium alloys

Autor: Turque, I., Chosson, R., Le Saux, M., C Brachet, J., Vandenberghe, V., Crepin, J., Anne-Françoise Gourgues-Lorenzon

Publikováno v: 18th International Symposium on Zirconium in the Nuclear Industry
18th International Symposium on Zirconium in the Nuclear Industry, May 2016, Hilton Head, United States
HAL

International audience; During a hypothetical loss-of-coolant accident (LOCA), zirconium alloy fuel claddings can be loaded by internal pressure and exposed to steam at high temperature (HT, potentially up to 1200°C) until they are cooled and water

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::0f91d0830c3500c2a4c138be555e6905
https://hal-cea.archives-ouvertes.fr/cea-02442337/file/201600000367.pdf

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