International audienceDuring reactivity initiated accident, the importance of cladding tube oxidation on its thermomechanical behavior has been investigated. After RIA tests in experimental reactors, oxide damage including radial cracking and spallation of the outer oxide layer has been evidenced. This work aims at better understanding the key mechanisms controlling these phenomena. Laboratory air-oxidation of Zircaloy-4 cladding tubes has been performed at 470 °C. SEM micrographs show that radial cracks are initiated from the outer surface of the oxide layer and propagated radially towards the oxide-metal interface. A model predicting the stress evolution within the oxide and the depth of radial cracks has been developed and validated on l...
The oxide scale growth in high temperature oxidation leads to generation of stresses in the oxide/me...
In Pressurised Water Reactor fuel assemblies, cladding tubes constitute the first safety barriers ag...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...
International audienceDuring reactivity initiated accident, the importance of cladding tube oxidatio...
En cas d'accident de réactivité, le comportement thermomécanique des gaines de crayons de combustibl...
International audienceIn the frame of its research work on nuclear fuel safety, the French “Institut...
In order to guarantee the integrity of nuclear fuel rod cladding, it is necessary for EDF to charact...
During hypothetical Loss-Of-Coolant-Accident (LOCA) scenarios, zirconium alloy fuel cladding tubes a...
Dans le cadre des études visant à garantir l'intégrité de la gaine du crayon combustible, EDF est am...
During the second stage of Loss Of Coolant Accident (LOCA) in Pressurized Water Reactors (PWR) zirco...
This thesis deals with the study of the creep behavior of pre-oxidized Zy-4 cladding under simulated...
Le comportement des assemblages combustibles des Réacteurs Nucléaires à Eau Pressurisée (REP) doit ê...
Lors d’un scénario hypothétique d’Accident par Perte de Réfrigérant Primaire (APRP), les gainages co...
The oxide scale growth in high temperature oxidation leads to generation of stresses in the oxide/me...
In Pressurised Water Reactor fuel assemblies, cladding tubes constitute the first safety barriers ag...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...
International audienceDuring reactivity initiated accident, the importance of cladding tube oxidatio...
En cas d'accident de réactivité, le comportement thermomécanique des gaines de crayons de combustibl...
International audienceIn the frame of its research work on nuclear fuel safety, the French “Institut...
In order to guarantee the integrity of nuclear fuel rod cladding, it is necessary for EDF to charact...
During hypothetical Loss-Of-Coolant-Accident (LOCA) scenarios, zirconium alloy fuel cladding tubes a...
Dans le cadre des études visant à garantir l'intégrité de la gaine du crayon combustible, EDF est am...
During the second stage of Loss Of Coolant Accident (LOCA) in Pressurized Water Reactors (PWR) zirco...
This thesis deals with the study of the creep behavior of pre-oxidized Zy-4 cladding under simulated...
Le comportement des assemblages combustibles des Réacteurs Nucléaires à Eau Pressurisée (REP) doit ê...
Lors d’un scénario hypothétique d’Accident par Perte de Réfrigérant Primaire (APRP), les gainages co...
The oxide scale growth in high temperature oxidation leads to generation of stresses in the oxide/me...
In Pressurised Water Reactor fuel assemblies, cladding tubes constitute the first safety barriers ag...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...