In pressurized water reactors of nuclear power plants, fuel pellets are contained in cladding tubes, made of Zirconium alloy, for instance Zircaloy-4. During their life in the primary water of the reactor (155 bars, 300°C), cladding tubes are oxidized and consequently hydrided. A part of the hydrogen given off precipitates as Zirconium hydrides in the bulk material and embrittles the material. This embitterment depends on many parameters, among which hydrogen content and orientation of hydrides with respect to the applied stress. This investigation is devoted to the influence of the orientation of hydrides with respect to the applied stress on strain, damage and failure mechanisms. Macroscopic and SEM in-situ ring tensile tests are performe...
International audienceThe influence of a hydrogen concentration gradient at the crack-tip and hydrid...
Spent nuclear fuel claddings discharged from water reactors contain hydrogen up to 800 wppm dependin...
International audienceThis work is part of the global research effort carried out at the CEA to impr...
In pressurized water reactors of nuclear power plants, fuel pellets are contained in cladding tubes,...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
The purpose of this study is to characterize and simulate the mechanical behaviour and failure of fr...
Due to their low thermal neutron capture cross-section, adequate mechanical strength and high corros...
Zircaloy-4 is widely used as a nuclear fuel cladding material in light water reactors (LWRs). Howeve...
A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized b...
In the frame of its research activity on nuclear fuel safety, the French "Institut de Radioprotectio...
An experimental setup was designed, fabricated and used to form radial hydrides in Zr-2.5%Nb alloy p...
Hydride formation is one of the main degradation mechanisms of zirconium alloys in hydrogen-rich env...
In this paper, we focus mainly on evaluating the anisotropy evolution in Zircaloy-4 tubes with respe...
International audiencePrecipitation of radial hydrides in zirconium-based cladding concomitant with ...
Hydrogen in excess of the terminal solid solubility precipitates out as a brittle hydride phase in z...
International audienceThe influence of a hydrogen concentration gradient at the crack-tip and hydrid...
Spent nuclear fuel claddings discharged from water reactors contain hydrogen up to 800 wppm dependin...
International audienceThis work is part of the global research effort carried out at the CEA to impr...
In pressurized water reactors of nuclear power plants, fuel pellets are contained in cladding tubes,...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
The purpose of this study is to characterize and simulate the mechanical behaviour and failure of fr...
Due to their low thermal neutron capture cross-section, adequate mechanical strength and high corros...
Zircaloy-4 is widely used as a nuclear fuel cladding material in light water reactors (LWRs). Howeve...
A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized b...
In the frame of its research activity on nuclear fuel safety, the French "Institut de Radioprotectio...
An experimental setup was designed, fabricated and used to form radial hydrides in Zr-2.5%Nb alloy p...
Hydride formation is one of the main degradation mechanisms of zirconium alloys in hydrogen-rich env...
In this paper, we focus mainly on evaluating the anisotropy evolution in Zircaloy-4 tubes with respe...
International audiencePrecipitation of radial hydrides in zirconium-based cladding concomitant with ...
Hydrogen in excess of the terminal solid solubility precipitates out as a brittle hydride phase in z...
International audienceThe influence of a hydrogen concentration gradient at the crack-tip and hydrid...
Spent nuclear fuel claddings discharged from water reactors contain hydrogen up to 800 wppm dependin...
International audienceThis work is part of the global research effort carried out at the CEA to impr...