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...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
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...
International audienceIn Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) sc...
International audienceIn Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) sc...
International audienceIn Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) sc...
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 audienceChromium-coated zirconium alloys are being studied as Enhanced Accident Tolera...
International audienceChromium-coated zirconium alloys are being studied as Enhanced Accident Tolera...
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...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
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...
International audienceIn Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) sc...
International audienceIn Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) sc...
International audienceIn Light Water Reactors, under hypothetical LOss of Coolant Accident (LOCA) sc...
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 audienceChromium-coated zirconium alloys are being studied as Enhanced Accident Tolera...
International audienceChromium-coated zirconium alloys are being studied as Enhanced Accident Tolera...
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...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
International audienceTo improve the safety of nuclear power plants, a Cr protective layer is deposi...
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...