Modeling fuel behavior requires an accurate description of the cladding stress response for both operational and safety considerations. The transient creep response of Zirconium alloys is commonly modeled using a strain hardening rule which is known to hold in cases with monotonously increasing stresses. However, the strain hardening rule is experimentally known to fail in scenarios such as load drop or reversal. In this paper we derive a simple and easily implementable set of rules for primary creep based on experimental results which contradict the strain hardening rule. The primary creep predicted by these rules is compared with data from published thermal creep experiments and Halden in-pile creep experiment IFA-585. The model thus crea...
International audienceFuel cladding tubes, made of zirconium alloys are subjected, in-reactor, to a ...
International audienceA custom experimental setup has been designed to investigate the secondary cre...
In many high temperature applications the accumulation of creep strain during the primary stage cann...
Modeling fuel behavior requires an accurate description of the cladding stress response for both ope...
In fuel behaviour modelling accurate description of the cladding stress response is important for bo...
The cladding of the nuclear fuel is subjected to varying conditions during fuel reactor life. Conven...
The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial rea...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
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...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postula...
International audienceFuel cladding tubes, made of zirconium alloys are subjected, in-reactor, to a ...
International audienceA custom experimental setup has been designed to investigate the secondary cre...
In many high temperature applications the accumulation of creep strain during the primary stage cann...
Modeling fuel behavior requires an accurate description of the cladding stress response for both ope...
In fuel behaviour modelling accurate description of the cladding stress response is important for bo...
The cladding of the nuclear fuel is subjected to varying conditions during fuel reactor life. Conven...
The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial rea...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
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...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postula...
International audienceFuel cladding tubes, made of zirconium alloys are subjected, in-reactor, to a ...
International audienceA custom experimental setup has been designed to investigate the secondary cre...
In many high temperature applications the accumulation of creep strain during the primary stage cann...