International audienceIn Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) scenario, zirconium alloy nuclear fuel claddings undergo significant steam oxidation at high temperatures. In such accidental situation, decreasing the oxidation rate of nuclear fuel claddings is a key issue to improve the accident tolerance of the nuclear fuel sub-assembly. Hence, CEA has engaged specific studies on chromium-coated zirconium alloys in the framework of CEA-FRAMATOME-EDF collaborative program on Enhanced Accident Tolerant Fuel (E-ATF) cladding materials. Beyond the LOCA issues, the adhesion strength of the Cr coating has to be assessed under irradiation. Thus, the purpose of the study is to determine the Cr hardening and the sta...
Heavy ion (6 MeV Au+) irradiation studies were carried out on three candidate coatings (Cr, CrN, TiA...
International audienceFor enhanced accident tolerant fuels for light water reactors application, chr...
The performance of Cr-coated Optimized ZIRLO™ as accident tolerant fuel cladding material for pressu...
International audienceIn Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) sc...
International audienceChromium-coated zirconium alloys are being studied as Enhanced Accident Tolera...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
In Light Water Reactors (LWR) under hypothetical accidental conditions such as LOss of Coolant Accid...
Dans les Réacteurs à Eau Pressurisée (REP), en conditions hypothétiques accidentelles d'Accident de ...
International audienceHighly adherent, thin Cr coatings on Zr-based nuclear fuel claddings can be po...
The Fukushima-Daiichi accident revealed that the zirconium fuel claddings have the significant safet...
This study is a systematic investigation on the interface reactions of various coating materials for...
International audienceChromium coatings aiming to protect the current zirconium alloy nuclear fuel c...
The Fukushima Daiichi reactor accident showed that Zircaloy-4 fuel cladding tubes under accident con...
International audienceDuring the Fukushima Daiichi accident in 2011 the fuel rods underwent the degr...
Heavy ion (6 MeV Au+) irradiation studies were carried out on three candidate coatings (Cr, CrN, TiA...
International audienceFor enhanced accident tolerant fuels for light water reactors application, chr...
The performance of Cr-coated Optimized ZIRLO™ as accident tolerant fuel cladding material for pressu...
International audienceIn Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) sc...
International audienceChromium-coated zirconium alloys are being studied as Enhanced Accident Tolera...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
In Light Water Reactors (LWR) under hypothetical accidental conditions such as LOss of Coolant Accid...
Dans les Réacteurs à Eau Pressurisée (REP), en conditions hypothétiques accidentelles d'Accident de ...
International audienceHighly adherent, thin Cr coatings on Zr-based nuclear fuel claddings can be po...
The Fukushima-Daiichi accident revealed that the zirconium fuel claddings have the significant safet...
This study is a systematic investigation on the interface reactions of various coating materials for...
International audienceChromium coatings aiming to protect the current zirconium alloy nuclear fuel c...
The Fukushima Daiichi reactor accident showed that Zircaloy-4 fuel cladding tubes under accident con...
International audienceDuring the Fukushima Daiichi accident in 2011 the fuel rods underwent the degr...
Heavy ion (6 MeV Au+) irradiation studies were carried out on three candidate coatings (Cr, CrN, TiA...
International audienceFor enhanced accident tolerant fuels for light water reactors application, chr...
The performance of Cr-coated Optimized ZIRLO™ as accident tolerant fuel cladding material for pressu...