International audienceThis paper presents new experimental thermo-mechanical tests recently developed in order to understand the behaviour of fuel clads under anisothermal conditions. The experimental setups permitted material testing in complex conditions representative of real RIA loading (high strain and heating rates) coupling simultaneous mechanical and thermal loading. Mechanical properties are studied and compared to isothermal ones. Results showed a clear history effect at low strain rates, this effect seems to disappear at high strain rates due to rapid mechanical loading which limits heating before failure. 2D and 3D FEM are illustrated with applied thermo-mechanical loadings. These numerical simulations allowed us to evaluate the...
International audienceThis paper presents an assessment of the thermo-mechanical behavior of non-irr...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe thermo-mechanical behavior of Zircaloy-4 claddings under simulated post-DN...
International audienceThis paper presents new experimental thermo-mechanical tests recently develope...
International audienceThis paper presents a unified phenomenological model to describe the anisotrop...
Fuel clads made of zirconium alloys are the first safety barrier in the nuclear power plants. This w...
International audienceThe research aims at characterizing the thermal-mechanical behavior of fresh Z...
Les gaines combustibles conçues en alliages de zirconium constituent la première barrière de confine...
International audienceThe present work aims at characterizing the thermal-mechanical behavior of as-...
The hypothetical scenario of a control rod ejection in a Pressurised Water Reactor leads to a Reacti...
Specimen geometries have been developed to determine the mechanical properties of irradiated Zircalo...
International audienceThis paper presents an assessment of the thermo-mechanical behavior of non-irr...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe thermo-mechanical behavior of Zircaloy-4 claddings under simulated post-DN...
International audienceThis paper presents new experimental thermo-mechanical tests recently develope...
International audienceThis paper presents a unified phenomenological model to describe the anisotrop...
Fuel clads made of zirconium alloys are the first safety barrier in the nuclear power plants. This w...
International audienceThe research aims at characterizing the thermal-mechanical behavior of fresh Z...
Les gaines combustibles conçues en alliages de zirconium constituent la première barrière de confine...
International audienceThe present work aims at characterizing the thermal-mechanical behavior of as-...
The hypothetical scenario of a control rod ejection in a Pressurised Water Reactor leads to a Reacti...
Specimen geometries have been developed to determine the mechanical properties of irradiated Zircalo...
International audienceThis paper presents an assessment of the thermo-mechanical behavior of non-irr...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe thermo-mechanical behavior of Zircaloy-4 claddings under simulated post-DN...