In fuel behaviour modelling accurate description of the cladding stress response is important for both operational and safety considerations. The cladding creep determines in part the width of the gas gap, the duration to pellet-cladding contact and the stresses to the cladding due to the pellet expansion. Conventionally the strain hardening rule has been used to describe the creep response to transient loads in engineering applications. However, it has been well documented that the strain hardening rule does not describe well results of tests with load drops or reversals. In our earlier work we have developed a model for primary creep which can be used to simulate the in- and out-of-pile creep tests. Since then several creep experiments ha...
The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial rea...
International audienceDuring hypothetical Loss-Of-Coolant-Accident (LOCA) scenarii, zirconium alloy ...
Predictive models play an important role for increasing the reliability of composite structures over...
In fuel behaviour modelling accurate description of the cladding stress response is important for bo...
Modeling fuel behavior requires an accurate description of the cladding stress response for both ope...
The cladding of the nuclear fuel is subjected to varying conditions during fuel reactor life. Conven...
In fuel behaviour modelling accurate description of the cladding mechanical response is important fo...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
International audienceThis study aims to identify the creep behavior of Zircaloy-4 fuel claddings un...
The report describes the initial creepdown tests of Zircaloy fuel cladding in which the surface disp...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
In light water reactors the nuclear fuel is in the form of uranium dioxide pellets stacked inside a ...
Transient creep data recorded during low stress viscous creep of α-Ti, α-Zr, β-Co and zircaloy-2 are...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial rea...
International audienceDuring hypothetical Loss-Of-Coolant-Accident (LOCA) scenarii, zirconium alloy ...
Predictive models play an important role for increasing the reliability of composite structures over...
In fuel behaviour modelling accurate description of the cladding stress response is important for bo...
Modeling fuel behavior requires an accurate description of the cladding stress response for both ope...
The cladding of the nuclear fuel is subjected to varying conditions during fuel reactor life. Conven...
In fuel behaviour modelling accurate description of the cladding mechanical response is important fo...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
International audienceThis study aims to identify the creep behavior of Zircaloy-4 fuel claddings un...
The report describes the initial creepdown tests of Zircaloy fuel cladding in which the surface disp...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
In light water reactors the nuclear fuel is in the form of uranium dioxide pellets stacked inside a ...
Transient creep data recorded during low stress viscous creep of α-Ti, α-Zr, β-Co and zircaloy-2 are...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial rea...
International audienceDuring hypothetical Loss-Of-Coolant-Accident (LOCA) scenarii, zirconium alloy ...
Predictive models play an important role for increasing the reliability of composite structures over...