International audienceThe I-SCC behavior of cold-worked stress-relieved (CWSR) Zircaloy-4 was investigated by means of internal pressure tests in both inert and gaseous iodine environments. I-SCC susceptibility was derived from tests on both un-irradiated and neutron-irradiated claddings tubes. Crack propagation rates were obtained from tests on pre-cracked tubes. The internal pressure tests conducted on un-irradiated cold-worked stress-relieved Zircaloy-4 cladding tubes in an iodine vapor environment were used to investigate the influence of loading mode (either constant pressure tests, constant circumferential strain rate tests, or constant circumferential strain tests) and test temperature (320DC to 488DC) on the I-SCC process. The exper...
The deformation behaviour, burst pressure and fracture appearance of stress relieved Zircaloy-4 clad...
Stress corrosion cracking can cause failures of CANDU ® Zircaloy-4 fuel sheathing. A series of stati...
During the pellet-cladding interaction, Zirconium-alloy fuel claddings might fail when subjected to ...
International audienceThe I-SCC behavior of cold-worked stress-relieved (CWSR) Zircaloy-4 was invest...
International audienceThe I-SCC behavior of cold-worked stress-relieved (CWSR) Zircaloy-4 was invest...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
During accidental power transient conditions with Pellet Cladding Interaction (PCI), the synergistic...
Stress corrosion cracking (SCC) in unirradiated recrystallized Zircaloy-4 internally pressurized tub...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
International audienceZirconium alloys are widely used in the nuclear industry as cladding material ...
International audienceZirconium alloys are widely used in the nuclear industry as cladding material ...
A crack-growth model of stress corrosion cracking has been successfully applied to predict times-to-...
The segmented exp and ing m and rel test (SEMT) method is generally regarded as a good laboratory si...
The deformation behaviour, burst pressure and fracture appearance of stress relieved Zircaloy-4 clad...
Stress corrosion cracking can cause failures of CANDU ® Zircaloy-4 fuel sheathing. A series of stati...
During the pellet-cladding interaction, Zirconium-alloy fuel claddings might fail when subjected to ...
International audienceThe I-SCC behavior of cold-worked stress-relieved (CWSR) Zircaloy-4 was invest...
International audienceThe I-SCC behavior of cold-worked stress-relieved (CWSR) Zircaloy-4 was invest...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
During accidental power transient conditions with Pellet Cladding Interaction (PCI), the synergistic...
Stress corrosion cracking (SCC) in unirradiated recrystallized Zircaloy-4 internally pressurized tub...
International audienceDuring accidental power transient conditions with Pellet Cladding Interaction ...
International audienceZirconium alloys are widely used in the nuclear industry as cladding material ...
International audienceZirconium alloys are widely used in the nuclear industry as cladding material ...
A crack-growth model of stress corrosion cracking has been successfully applied to predict times-to-...
The segmented exp and ing m and rel test (SEMT) method is generally regarded as a good laboratory si...
The deformation behaviour, burst pressure and fracture appearance of stress relieved Zircaloy-4 clad...
Stress corrosion cracking can cause failures of CANDU ® Zircaloy-4 fuel sheathing. A series of stati...
During the pellet-cladding interaction, Zirconium-alloy fuel claddings might fail when subjected to ...