International audienceIrradiation damage in fuel cladding material is mainly caused by the neutron flux that results from fission reactions occurring in the fuel. To avoid the constraints inherent in handling radioactive material, the irradiation effects on the corrosion resistance of zirconium alloys can be studied by irradiating the materials with ions. We performed an original experiment using ion irradiation to more specifically study the influence of irradiation damage in the oxide on the corrosion rate of M5®. It has been established that irradiation with a 1.3-MeV helium ion at a fluence of 1017 cm−2 results in significant modifications of oxide properties, oxygen diffusion flux, and oxidation kinetics, as evidenced by Raman spectros...
Zirconium alloys are used for nuclear reactor fuel cladding and structural components, but aqueous c...
The objective of this research is to determine the effects of radiation-induced displacement damage ...
In an accelerator-driven system (ADS), the beam window material of the spallation neutron target is ...
International audienceIrradiation damage in fuel cladding material is mainly caused by the neutron f...
International audienceThe oxidation rate of Zircaloy-4 fuel cladding in nuclear reactor strongly inc...
International audienceA strong increase of the oxidation rate of Zircaloy-4 fuel cladding is observe...
This thesis is part of the MUZIC-3 (Mechanistic Understanding of Zirconium Corrosion) project, with ...
A detailed study has been carried out on recrystallised Zr-1.0Nb alloys corroded and irradiated unde...
International audienceThe oxidation kinetics acceleration observed in Zircaloy-4 cladding in Pressur...
International audienceThe corrosion process (oxidation and hydriding) of the zirconium alloy claddin...
International audienceThe good corrosion resistance of the M5Framatome cladding used in pressurised ...
[[abstract]]In previous studies of irradiation effects on the nodular corrosion resistance of Zircal...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years i...
Le combustible nucléaire des Réacteurs à Eau sous Pression (REP), sous forme de pastilles d’oxyde d’...
[[abstract]]Specimens of Zircaloy-2 plate were irradiated with 2 MeV proton at 350 °C up to tota...
Zirconium alloys are used for nuclear reactor fuel cladding and structural components, but aqueous c...
The objective of this research is to determine the effects of radiation-induced displacement damage ...
In an accelerator-driven system (ADS), the beam window material of the spallation neutron target is ...
International audienceIrradiation damage in fuel cladding material is mainly caused by the neutron f...
International audienceThe oxidation rate of Zircaloy-4 fuel cladding in nuclear reactor strongly inc...
International audienceA strong increase of the oxidation rate of Zircaloy-4 fuel cladding is observe...
This thesis is part of the MUZIC-3 (Mechanistic Understanding of Zirconium Corrosion) project, with ...
A detailed study has been carried out on recrystallised Zr-1.0Nb alloys corroded and irradiated unde...
International audienceThe oxidation kinetics acceleration observed in Zircaloy-4 cladding in Pressur...
International audienceThe corrosion process (oxidation and hydriding) of the zirconium alloy claddin...
International audienceThe good corrosion resistance of the M5Framatome cladding used in pressurised ...
[[abstract]]In previous studies of irradiation effects on the nodular corrosion resistance of Zircal...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years i...
Le combustible nucléaire des Réacteurs à Eau sous Pression (REP), sous forme de pastilles d’oxyde d’...
[[abstract]]Specimens of Zircaloy-2 plate were irradiated with 2 MeV proton at 350 °C up to tota...
Zirconium alloys are used for nuclear reactor fuel cladding and structural components, but aqueous c...
The objective of this research is to determine the effects of radiation-induced displacement damage ...
In an accelerator-driven system (ADS), the beam window material of the spallation neutron target is ...