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Akademický článek

Assessment of a new fabrication route for Fe–9Cr–1W ODS cladding tubes

Autor: Toualbi, L., Cayron, C., Olier, P., Malaplate, J., Praud, M., Mathon, M.-H., Bossu, D., Rouesne, E., Montani, A., Logé, R., de Carlan, Y.

Publikováno v: In Journal of Nuclear Materials September 2012 428(1-3):47-53

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Akademický článek

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Akademický článek

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Effect of chromium grain size and morphology on the HT oxidation behavior of chromium coated Zr based alloys

Autor: Chaabane-Jebali, N., Brachet, Jc., Lesaux, M., Hamon, D., Rouesne, E., Urvoy, S., Tabarant, M., Schlegel, M., Lomello, F.

Publikováno v: Materials Science and Engineering 2019
Materials Science and Engineering 2019, Feb 2019, San-Francisco, United States

International audience; One of the hypothetical accidents studied in the field of the safety studies of Pressurized light Water Reactors (PWR) is the Loss-Of-Coolant Accident (LOCA). In this scenario, zirconium alloy fuel claddings could undergo a hi

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::1d82db8e58b9d4837ee716b200398bf3
https://hal.science/hal-02411074

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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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Chromium hardening and Zr-Cr interface stability of irradiated chromium-coated Zircaloy-4 alloy

Autor: Ribis, J., Wu, A., Brachet, Jc., Clouet, E., Arnal, Benoît, Rouesne, E., Urvoy, S., Barcelo, F., Gentils, A., Baumier, C., Rancoeur, L., Robert, Y., Leprêtre, F., Bischoff, J., Pouillier, E.

Publikováno v: Numat 2018
Numat 2018, Oct 2018, Seattle, United States

International audience; In Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) scenario, zirconium alloy nuclear fuel claddings undergo significant steam oxidation at high temperatures. In such accidental situation, decreasing th

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::226fb1fc8483ff2c9171ae55e154c2f8
https://cea.hal.science/cea-02400192

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Structural evolutions and internal stresses in Zr alloys during oxidation at high temperature and subsequent cooling

Autor: Guillou, R., Lesaux, M., Brachet, J.-C., Hamon, D., Rouesne, E., Toffolon-Masclet, C., Bechade, J.-L., Menut, D., Thiaudiere, D.

Publikováno v: Thermec 2018-International Conference on PROCESSING & MANUFACTURING OF ADVANCED MATERIALS
Thermec 2018-International Conference on PROCESSING & MANUFACTURING OF ADVANCED MATERIALS, Jul 2018, Paris, France

International audience

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::4a544b763f75ea78b9c8057d6ebfc0d8
https://cea.hal.science/cea-02338566

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