International audienceThe aim of this work is to study strain and fracture mechanisms of zircaloy 4 tubes used in Pressurized Water Reactor and submitted to a compaction test. To reach this goal, work hardened zircaloy 4 has been validated - from a mechanical point of view - as a representative material of the irradiated one. A numerical study allows to model the compaction test. Validations are performed on Load/Displacement curves, and special attention is paid to numerical developments in fracture mechanics. Besides, oxidation has been carried out in autoclave in order to study its influence on the mechanical properties of work hardened zircaloy 4
The quenching of LWR cladding is investigated in order to understand the behaviour of a LWR core dur...
International audienceDuring a Loss of Coolant Accident in a Pressurized Water Reactor, a break on t...
In Pressurised Water Reactor fuel assemblies, cladding tubes constitute the first safety barriers ag...
International audienceThe aim of this work is to study strain and fracture mechanisms of zircaloy 4 ...
International audienceIn the frame of its research work on nuclear fuel safety, the French “Institut...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...
Specimen geometries have been developed to determine the mechanical properties of irradiated Zircalo...
International audienceDuring reactivity initiated accident, the importance of cladding tube oxidatio...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
International audienceFuel cladding tubes, made of zirconium alloys are subjected, in-reactor, to a ...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
International audienceDuring a Loss of Coolant Accident in a Pressurized Water Reactor, a break on t...
International audienceIn the frame of its research activity on nuclear fuel safety, the French "Inst...
The quenching of LWR cladding is investigated in order to understand the behaviour of a LWR core dur...
International audienceDuring a Loss of Coolant Accident in a Pressurized Water Reactor, a break on t...
In Pressurised Water Reactor fuel assemblies, cladding tubes constitute the first safety barriers ag...
International audienceThe aim of this work is to study strain and fracture mechanisms of zircaloy 4 ...
International audienceIn the frame of its research work on nuclear fuel safety, the French “Institut...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...
Specimen geometries have been developed to determine the mechanical properties of irradiated Zircalo...
International audienceDuring reactivity initiated accident, the importance of cladding tube oxidatio...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
International audienceFuel cladding tubes, made of zirconium alloys are subjected, in-reactor, to a ...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
International audienceDuring a Loss of Coolant Accident in a Pressurized Water Reactor, a break on t...
International audienceIn the frame of its research activity on nuclear fuel safety, the French "Inst...
The quenching of LWR cladding is investigated in order to understand the behaviour of a LWR core dur...
International audienceDuring a Loss of Coolant Accident in a Pressurized Water Reactor, a break on t...
In Pressurised Water Reactor fuel assemblies, cladding tubes constitute the first safety barriers ag...