During hypothetical Loss-Of-Coolant-Accident (LOCA) scenarios, zirconium alloy fuel cladding tubes are subjected to severe thermo- mechanical loading conditions in highly oxidising chemical environments. Pressure and temperature evolution together with cooling water can lead to ballooning and burst followed by steam oxidation and hydrogen uptake at high temperature, and then axial loading during the final reflooding stage.This study focuses on the identification of mechanisms and key parameters which drive cladding fracture during the reflooding stage under axial tensile load.Laboratory-scale semi-integral tests simulating LOCA transients on Zircaloy−4 test rods have been realised. A fracture/no-fracture threshold of oxidation duration at h...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...
International audienceMechanical behavior at high temperature of highly oxygen-or hydrogen-enriched ...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
During hypothetical Loss-Of-Coolant-Accident (LOCA) scenarios, zirconium alloy fuel cladding tubes a...
Lors d’un scénario hypothétique d’Accident par Perte de Réfrigérant Primaire (APRP), les gainages co...
During the second stage of Loss Of Coolant Accident (LOCA) in Pressurized Water Reactors (PWR) zirco...
International audienceThis work addressed fracture mechanisms of nuclear fuel claddings in hypotheti...
In order to guarantee the integrity of nuclear fuel rod cladding, it is necessary for EDF to charact...
Le comportement des assemblages combustibles des Réacteurs Nucléaires à Eau Pressurisée (REP) doit ê...
Dans le cadre des études visant à garantir l'intégrité de la gaine du crayon combustible, EDF est am...
Under hypothetical loss-of-coolant accident conditions, fuel cladding tubes made of zirconium alloys...
International audienceDuring reactivity initiated accident, the importance of cladding tube oxidatio...
This thesis deals with the study of the creep behavior of pre-oxidized Zy-4 cladding under simulated...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...
International audienceMechanical behavior at high temperature of highly oxygen-or hydrogen-enriched ...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
During hypothetical Loss-Of-Coolant-Accident (LOCA) scenarios, zirconium alloy fuel cladding tubes a...
Lors d’un scénario hypothétique d’Accident par Perte de Réfrigérant Primaire (APRP), les gainages co...
During the second stage of Loss Of Coolant Accident (LOCA) in Pressurized Water Reactors (PWR) zirco...
International audienceThis work addressed fracture mechanisms of nuclear fuel claddings in hypotheti...
In order to guarantee the integrity of nuclear fuel rod cladding, it is necessary for EDF to charact...
Le comportement des assemblages combustibles des Réacteurs Nucléaires à Eau Pressurisée (REP) doit ê...
Dans le cadre des études visant à garantir l'intégrité de la gaine du crayon combustible, EDF est am...
Under hypothetical loss-of-coolant accident conditions, fuel cladding tubes made of zirconium alloys...
International audienceDuring reactivity initiated accident, the importance of cladding tube oxidatio...
This thesis deals with the study of the creep behavior of pre-oxidized Zy-4 cladding under simulated...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...
International audienceMechanical behavior at high temperature of highly oxygen-or hydrogen-enriched ...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...