When Zirconium claddings are exposed to irradiation and oxidation in reactor, after a certain period, they may undergo a change of hydrogen uptake behavior and in some cases an increased hydrogen pickup fraction. Hydrogen is present in reactor as a by-product of the oxidation, or through radiolysis of the coolant. It may penetrate through the oxide and enter the underlying metal. Above a certain concentration, it precipitates as brittle Zr-hydrides degrading the cladding’s mechanical properties. The work performed in this study contributes to the improved understanding of the hydrogen uptake mechanism in reactor. Parameters, which have been suggested to contribute to the changes in hydrogen uptake at high burnups, have been clearly quant...
International audienceWhile Zircaloy-4 alloy shows a high and constant hydrogen pickup fraction over...
International audienceThis study is focused on the hydrogen-induced dimensional change or "growth" o...
International audienceDuring hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear ...
In light water reactors the fuel is encapsulated in Zr-based claddings that withstand the harsh envi...
Zirconium-based fuel cladding used in nuclear reactors is susceptible to significant hydrogen uptake...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
Les alliages de zirconium sont utilisés comme matériaux de gainage dans les Réacteurs à Eau Pressuri...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
En conditions hypothétiques d’accident par perte de réfrigérant primaire, la gaine en alliage de zir...
This thesis is part of the MUZIC-3 (Mechanistic Understanding of Zirconium Corrosion) project, with ...
International audienceWhile Zircaloy-4 alloy shows a high and constant hydrogen pickup fraction over...
International audienceWhile Zircaloy-4 alloy shows a high and constant hydrogen pickup fraction over...
International audienceThis study is focused on the hydrogen-induced dimensional change or "growth" o...
International audienceDuring hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear ...
In light water reactors the fuel is encapsulated in Zr-based claddings that withstand the harsh envi...
Zirconium-based fuel cladding used in nuclear reactors is susceptible to significant hydrogen uptake...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
Les alliages de zirconium sont utilisés comme matériaux de gainage dans les Réacteurs à Eau Pressuri...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
En conditions hypothétiques d’accident par perte de réfrigérant primaire, la gaine en alliage de zir...
This thesis is part of the MUZIC-3 (Mechanistic Understanding of Zirconium Corrosion) project, with ...
International audienceWhile Zircaloy-4 alloy shows a high and constant hydrogen pickup fraction over...
International audienceWhile Zircaloy-4 alloy shows a high and constant hydrogen pickup fraction over...
International audienceThis study is focused on the hydrogen-induced dimensional change or "growth" o...
International audienceDuring hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear ...