International audienceZirconium alloys are widely used in the nuclear industry. Several components, such as cladding or guide tubes, undergo strong mechanical loading during and after their use inside the pressurized water reactors. The current requirements on higher fuel performances lead to the developing on new Zr based alloys exhibiting better mechanical properties. In this framework, creep behaviors of recrystallized Zircaloy-4 and M5™, have been investigated and then compared. In order to give a better understanding of the thermal creep anisotropy of Zr-based alloys, multi-axial creep tests have been carried out at 673K. Using a specific device, creep conditions have been set using different values of β=σzz/σθθ, σzz and σθθ...
In recent studies, the creep rate of Zircaloy-4, one of the basic property parameters of the nuclear...
This paper presents experimental data regarding creep behaviour of a Zr-1 wt% Nb alloy at elevated (...
International audienceThe temperatures of α → β transformation for the Zircaloy-4 and Zr–1%NbO alloy...
International audienceZirconium alloys are widely used in the nuclear industry. Several components, ...
Cladding tubes are structural parts of nuclear plants, submitted to complex thermomechanical loading...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
Zirconium alloy tubing is used in pressurized water nuclear reactors in order to prevent fissile mat...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
International audienceZirconium alloys used as cladding tubes for the fuel of Pressurized Water Reac...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
High-temperature (≈ 900−1400 K) steady-state creep test data on as-received zirconium alloys, Zr-1wt...
Tensile creep behavior of the Zr-2.5Nb alloy has been studied through tests under constant load (str...
In recent studies, the creep rate of Zircaloy-4, one of the basic property parameters of the nuclear...
This paper presents experimental data regarding creep behaviour of a Zr-1 wt% Nb alloy at elevated (...
International audienceThe temperatures of α → β transformation for the Zircaloy-4 and Zr–1%NbO alloy...
International audienceZirconium alloys are widely used in the nuclear industry. Several components, ...
Cladding tubes are structural parts of nuclear plants, submitted to complex thermomechanical loading...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
Zirconium alloy tubing is used in pressurized water nuclear reactors in order to prevent fissile mat...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
International audienceZirconium alloys used as cladding tubes for the fuel of Pressurized Water Reac...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
High-temperature (≈ 900−1400 K) steady-state creep test data on as-received zirconium alloys, Zr-1wt...
Tensile creep behavior of the Zr-2.5Nb alloy has been studied through tests under constant load (str...
In recent studies, the creep rate of Zircaloy-4, one of the basic property parameters of the nuclear...
This paper presents experimental data regarding creep behaviour of a Zr-1 wt% Nb alloy at elevated (...
International audienceThe temperatures of α → β transformation for the Zircaloy-4 and Zr–1%NbO alloy...