International audienceA strong increase of the oxidation rate of Zircaloy-4 fuel cladding is observed for burnups above 35 GWd/MtU in PWR This kinetic acceleration could be in large part due to the irradiation damage. To quantify the effect of the oxide layer irradiation on the Zircaloy-4 corrosion rate, a new approach was used. Defects created by light ion irradiation increase the oxidation rate of the alloy up to 23 days in autoclave in agreement with the irradiation defect annealing characterized by RAMAN spectroscopy. A simple model taking into account the annealing of the irradiation defect is proposed to explain the results
International audienceChromium-coated zirconium alloys are being studied as Enhanced Accident Tolera...
We report for the first time the observation of irradiation-induced amorphization of the zirconium s...
Zirconium alloys are often used as nuclear fuel cladding. During transients the cladding may be expo...
International audienceA strong increase of the oxidation rate of Zircaloy-4 fuel cladding is observe...
International audienceThe oxidation rate of Zircaloy-4 fuel cladding in nuclear reactor strongly inc...
International audienceIrradiation damage in fuel cladding material is mainly caused by the neutron f...
International audienceThe oxidation kinetics acceleration observed in Zircaloy-4 cladding in Pressur...
International audienceThe corrosion process (oxidation and hydriding) of the zirconium alloy claddin...
The effect of oxidation time on the characteristics and mechanical properties of spent nuclear fuel ...
[[abstract]]Specimens of Zircaloy-2 plate were irradiated with 2 MeV proton at 350 °C up to tota...
This thesis is part of the MUZIC-3 (Mechanistic Understanding of Zirconium Corrosion) project, with ...
[[abstract]]In previous studies of irradiation effects on the nodular corrosion resistance of Zircal...
A one dimensional numerical model is presented to predict oxide scale growth and failure in zirconiu...
International audienceChromium-coated zirconium alloys are being studied as Enhanced Accident Tolera...
We report for the first time the observation of irradiation-induced amorphization of the zirconium s...
Zirconium alloys are often used as nuclear fuel cladding. During transients the cladding may be expo...
International audienceA strong increase of the oxidation rate of Zircaloy-4 fuel cladding is observe...
International audienceThe oxidation rate of Zircaloy-4 fuel cladding in nuclear reactor strongly inc...
International audienceIrradiation damage in fuel cladding material is mainly caused by the neutron f...
International audienceThe oxidation kinetics acceleration observed in Zircaloy-4 cladding in Pressur...
International audienceThe corrosion process (oxidation and hydriding) of the zirconium alloy claddin...
The effect of oxidation time on the characteristics and mechanical properties of spent nuclear fuel ...
[[abstract]]Specimens of Zircaloy-2 plate were irradiated with 2 MeV proton at 350 °C up to tota...
This thesis is part of the MUZIC-3 (Mechanistic Understanding of Zirconium Corrosion) project, with ...
[[abstract]]In previous studies of irradiation effects on the nodular corrosion resistance of Zircal...
A one dimensional numerical model is presented to predict oxide scale growth and failure in zirconiu...
International audienceChromium-coated zirconium alloys are being studied as Enhanced Accident Tolera...
We report for the first time the observation of irradiation-induced amorphization of the zirconium s...
Zirconium alloys are often used as nuclear fuel cladding. During transients the cladding may be expo...