International audienceIn the frame of its research activity on nuclear fuel safety, the French "Institut de Radioprotection et de Sûreté Nuclé aire" (IRSN) has been investigating the dimensional stability of fuel assemblies in Pressurized Water Reactors (PWR). Under normal operating conditions, the dimensional stability is an important performance issue for light water reactor fuel assemblies. The dimensional change results from a combined influence of oxidation, hydriding, irradiation growth and irradiation creep. In the present work, detailed studies carried out on zirconium alloys address the combined influence of oxide layer growth, hydride precipitation and thermal creep. In order to quantify the contribution of each parameter, three k...
Zircaloy-4 is widely used as a nuclear fuel cladding material in light water reactors (LWRs). Howeve...
[[abstract]]Zircaloy-4 plate specimens were gaseously hydrided up to 220 ppm H and then tested in a ...
International audienceThe creep behaviour of pre-oxidized and pre-hydrided Zircaloy-4 was investigat...
In the frame of its research activity on nuclear fuel safety, the French "Institut de Radioprotectio...
International audienceDuring a Loss of Coolant Accident in a Pressurized Water Reactor, a break on t...
International audienceDuring a Loss of Coolant Accident in a Pressurized Water Reactor, a break on t...
Zircaloy-4 is widely used in light water reactors (LWRs) for fuel cladding applications because of i...
Due to their low thermal neutron capture cross-section, adequate mechanical strength and high corros...
International audiencePrecipitation of radial hydrides in zirconium-based cladding concomitant with ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThis study is focused on the hydrogen-induced dimensional change or "growth" o...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
AbstractTo investigate the effect of hydrogen and oxygen contents on hydride reorientations during c...
Zircaloy-4 is widely used as a nuclear fuel cladding material in light water reactors (LWRs). Howeve...
[[abstract]]Zircaloy-4 plate specimens were gaseously hydrided up to 220 ppm H and then tested in a ...
International audienceThe creep behaviour of pre-oxidized and pre-hydrided Zircaloy-4 was investigat...
In the frame of its research activity on nuclear fuel safety, the French "Institut de Radioprotectio...
International audienceDuring a Loss of Coolant Accident in a Pressurized Water Reactor, a break on t...
International audienceDuring a Loss of Coolant Accident in a Pressurized Water Reactor, a break on t...
Zircaloy-4 is widely used in light water reactors (LWRs) for fuel cladding applications because of i...
Due to their low thermal neutron capture cross-section, adequate mechanical strength and high corros...
International audiencePrecipitation of radial hydrides in zirconium-based cladding concomitant with ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThis study is focused on the hydrogen-induced dimensional change or "growth" o...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
AbstractTo investigate the effect of hydrogen and oxygen contents on hydride reorientations during c...
Zircaloy-4 is widely used as a nuclear fuel cladding material in light water reactors (LWRs). Howeve...
[[abstract]]Zircaloy-4 plate specimens were gaseously hydrided up to 220 ppm H and then tested in a ...
International audienceThe creep behaviour of pre-oxidized and pre-hydrided Zircaloy-4 was investigat...