The PROMETRA program : A reliable material database for highly irradiated ZIRCALOY-4, ZIRLOTM and M5TM fuel claddings
Titre du congrès :SMIRT-18 International Conference on Structural Mechanics in Reactor Technology
Ville du congrès :Pékin
Date du congrès :07/08/2005
The assessment of the mechanical properties of the highly irradiated fuel claddings during an RIA (Reactivity Initiated Accident) has been carried out in the framework of the PROMETRA programme. Three main types of tests including burst tests, hoop and axial tensile tests, have been performed in CEA-Saclay hot laboratories in order to determine the cladding tensile properties used in the SCANAIR code. The representativeness of each test with regard to the RIA loading conditions can be addressed and analyzed in terms of strain or stress ratio. The present paper reports the high strain rate ductile mechanical properties of irradiated ZIRLOTM and M5TM alloys derived from the PROMETRA program and their comparison to the stress-relieved irradiated Zircaloy-4. Results of specific analysis of the behaviour of the 6 cycle M5TM and ZIRLOTM 75 GWd/tM for temperatures higher than 600°C are also presented.