The PROMETRA material testing program is a support program related to the study of high burnup fuel rod behavior under Reactivity Initiated Accidents (RIA) and to the interpretation of the CABRI REP-Na RIA test results. Hoop and axial tensile tests have been performed on fresh and irradiated Zircaloy-4 cladding alloy first at CEA Grenoble hot labs and now at CEA Saclay in order to assess the cladding mechanical behavior during RIA transients. Efforts have been continuously carried out in order to improve the prototipicallity of the tests for RIA studies involving new specimens and new testing techniques. The corrosion level of irradiated specimens reached up to 130 μm of oxide layer thickness. The influence of in-pile oxide layer spallation...
International audienceThe research aims at characterizing the thermal-mechanical behavior of fresh Z...
International audienceThis paper presents an assessment of the thermo-mechanical behavior of non-irr...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
The PROMETRA material testing program is a support program related to the study of high burnup fuel ...
International audienceAn assessment of the mechanical properties of the highly irradiated fuel cladd...
Specimen geometries have been developed to determine the mechanical properties of irradiated Zircalo...
International audienceA fuel cladding mechanical test, performed under conditions of plane strain de...
The French “Institut de Radioprotection et de Sîreté Nucléaire” (IRSN) conducted the REP-Na tests in...
The hypothetical scenario of a control rod ejection in a Pressurised Water Reactor leads to a Reacti...
A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized b...
International audienceThis paper presents a unified phenomenological model to describe the anisotrop...
International audienceThe research aims at characterizing the thermal-mechanical behavior of fresh Z...
International audienceThis paper presents an assessment of the thermo-mechanical behavior of non-irr...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
The PROMETRA material testing program is a support program related to the study of high burnup fuel ...
International audienceAn assessment of the mechanical properties of the highly irradiated fuel cladd...
Specimen geometries have been developed to determine the mechanical properties of irradiated Zircalo...
International audienceA fuel cladding mechanical test, performed under conditions of plane strain de...
The French “Institut de Radioprotection et de Sîreté Nucléaire” (IRSN) conducted the REP-Na tests in...
The hypothetical scenario of a control rod ejection in a Pressurised Water Reactor leads to a Reacti...
A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized b...
International audienceThis paper presents a unified phenomenological model to describe the anisotrop...
International audienceThe research aims at characterizing the thermal-mechanical behavior of fresh Z...
International audienceThis paper presents an assessment of the thermo-mechanical behavior of non-irr...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...