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