Add to ORKG3.00SIGLELD:9091.9F(ND-R--814(S)). / BLDSC - British Library Document Supply CentreGBUnited Kingdo
International audienceA custom experimental setup has been designed to investigate the secondary cre...
Modeling fuel behavior requires an accurate description of the cladding stress response for both ope...
International audienceDuring hypothetical Loss-Of-Coolant-Accident (LOCA) scenarii, zirconium alloy ...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postula...
International audienceThis study aims to identify the creep behavior of Zircaloy-4 fuel claddings un...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
Creep, a potential degradation mechanism of Zircaloy cladding after repository disposal of spent nuc...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Kar...
This experimental data report is Volume 4 of a series of 5 volumes describing the oxidation and defo...
The report describes the initial creepdown tests of Zircaloy fuel cladding in which the surface disp...
International audienceA custom experimental setup has been designed to investigate the secondary cre...
Modeling fuel behavior requires an accurate description of the cladding stress response for both ope...
International audienceDuring hypothetical Loss-Of-Coolant-Accident (LOCA) scenarii, zirconium alloy ...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postula...
International audienceThis study aims to identify the creep behavior of Zircaloy-4 fuel claddings un...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
Creep, a potential degradation mechanism of Zircaloy cladding after repository disposal of spent nuc...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Kar...
This experimental data report is Volume 4 of a series of 5 volumes describing the oxidation and defo...
The report describes the initial creepdown tests of Zircaloy fuel cladding in which the surface disp...
International audienceA custom experimental setup has been designed to investigate the secondary cre...
Modeling fuel behavior requires an accurate description of the cladding stress response for both ope...
International audienceDuring hypothetical Loss-Of-Coolant-Accident (LOCA) scenarii, zirconium alloy ...