International audienceIn order to improve the understanding of the microscopic phenomena occurring during irradiation in zirconium alloys, ion beam irradiations are performed at 350 DC (dose-rate of 2 × 10-5 dpa/s) on recrystallized Zy-4 and M5 alloys, with 2 MeV protons. The aim of this study is to determine in which way proton irradiations can be representative of neutron irradiations, considering the second phase particle changes and the influence of these changes on the microstructural evolution of the material during irradiation. The 2 MeV proton irradiation at 350 DC, performed here, seems to reproduces well what happened in Zy-4 in PWR conditions with a progressive amorphisation of the Zr(Fe,Cr)2 Laves phases, but with a lower growth...
Zirconium alloys have been successfully used as fuel cladding and structural materials in fission re...
Proton irradiation at temperatures of 310 and 350??C has been researched using 2 MeV proton to an at...
[[abstract]]Zircaloy-4 has been used extensively as fuel cladding and core structural material in li...
International audienceIn order to improve the understanding of the microscopic phenomena occurring d...
The stability of the β-Nb Second Phase Particles (SPPs) in two types of Zr–Nb alloys (recrystallised...
Although the evolution of irradiation-induced dislocation loops has been well correlated with irradi...
Detailed analysis was carried out on proton and a neutron irradiated Nb-containing Zr-alloy to study...
Recrystallized zirconium alloys, used as structural materials for the Pressurized Water Reactor fuel...
2 MeV proton radiation was performed at 350??C at damage levels of 2, 5 and 7 displacement per atom....
Zirconium alloys are used for nuclear reactor fuel cladding and structural components, but aqueous c...
[[abstract]]Various thermo-mechanically treated Zircaloy-4 specimens which were subjected to 1 MeV H...
Two types of Zr–0.8Sn–1Nb–0.3Fe Zr alloys were irradiated by krypton ions in the t...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
Ion-beam-analysis techniques are being used to provide an understanding of the nature of collision c...
In this study, APT and TEM analyses were used to characterise two Zr-based alloys neutron-irradiated...
Zirconium alloys have been successfully used as fuel cladding and structural materials in fission re...
Proton irradiation at temperatures of 310 and 350??C has been researched using 2 MeV proton to an at...
[[abstract]]Zircaloy-4 has been used extensively as fuel cladding and core structural material in li...
International audienceIn order to improve the understanding of the microscopic phenomena occurring d...
The stability of the β-Nb Second Phase Particles (SPPs) in two types of Zr–Nb alloys (recrystallised...
Although the evolution of irradiation-induced dislocation loops has been well correlated with irradi...
Detailed analysis was carried out on proton and a neutron irradiated Nb-containing Zr-alloy to study...
Recrystallized zirconium alloys, used as structural materials for the Pressurized Water Reactor fuel...
2 MeV proton radiation was performed at 350??C at damage levels of 2, 5 and 7 displacement per atom....
Zirconium alloys are used for nuclear reactor fuel cladding and structural components, but aqueous c...
[[abstract]]Various thermo-mechanically treated Zircaloy-4 specimens which were subjected to 1 MeV H...
Two types of Zr–0.8Sn–1Nb–0.3Fe Zr alloys were irradiated by krypton ions in the t...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
Ion-beam-analysis techniques are being used to provide an understanding of the nature of collision c...
In this study, APT and TEM analyses were used to characterise two Zr-based alloys neutron-irradiated...
Zirconium alloys have been successfully used as fuel cladding and structural materials in fission re...
Proton irradiation at temperatures of 310 and 350??C has been researched using 2 MeV proton to an at...
[[abstract]]Zircaloy-4 has been used extensively as fuel cladding and core structural material in li...