The PROMETRA Program: Fuel Cladding Mechanical Behavior under High Strain Rate

An assessment of the mechanical properties of the highly irradiated fuel claddings under high strain rate has been carried out in the framework of the PROMETRA program undertaken by the French Institut de Radioprotection et de Sûreté Nucléaire in collaboration with Electricité de France and Commissa...

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Bibliographic Details
Published in:Nuclear technology 2007-03, Vol.157 (3), p.215-229
Main Authors: Cazalis, B., Desquines, J., Poussard, C., Petit, M., Monerie, Y., Bernaudat, C., Yvon, P., Averty, X.
Format: Article
Language:English
Subjects:
Applied sciences
Energy
Energy. Thermal use of fuels
Engineering Sciences
Exact sciences and technology
Fission nuclear power plants
Fuels
Installations for energy generation and conversion: thermal and electrical energy
Nuclear fuels
Preparation and processing of nuclear fuels
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Summary:An assessment of the mechanical properties of the highly irradiated fuel claddings under high strain rate has been carried out in the framework of the PROMETRA program undertaken by the French Institut de Radioprotection et de Sûreté Nucléaire in collaboration with Electricité de France and Commissariat à l'Energie Atomique (CEA). Three types of tests, including burst tests, hoop and axial tensile tests, have been performed at CEA-Saclay hot laboratories to determine the cladding tensile properties to use in the SCANAIR code. The prototypicality of each test with regard to the reactivity-initiated accident loading conditions can be addressed and analyzed in terms of strain or stress ratio. The high-strain-rate ductile mechanical properties of irradiated ZIRLO and M5 alloys derived from the PROMETRA program and their comparison to the stress-relieved irradiated Zircaloy-4 are reported. Then, the clad brittle behavior, in particular for highly corroded or spalled Zircaloy-4 cladding, is investigated.
ISSN:0029-5450
1943-7471
DOI:10.13182/NT07-A3814