Development of ODS ferritic steel claddings for fast reactor fuels, 2; Material irradiation test in JOYO

Yamashita, Shinichiro   ; Yano, Yasuhide  ; Ogawa, Ryuichiro; Inoue, Masaki ; Yoshitake, Tsunemitsu 

Oxide dispersion strengthened (ODS) steel is a prospective cladding material for the advanced fuel claddings of fast reactors, owing to their excellent radiation resistance and high temperature strength capability. JAEA has been developed two types of 9Cr martensitic and 12Cr ferritic ODS steel claddings, and conducted the irradiation test for the accumulation of irradiation data as well as for the understanding of irradiation behavior of ODS steel claddings. In this study, post irradiation examination data on metallurgical examination, ring-tensile test, hardness measurement, microstructural observation, and chemical analysis were obtained, indicating that there were no significant degradations in mechanical property and also no changes in microstructure due to irradiation and that ODS steel claddings had good irradiation torelance.