[2D10-17] Accident-tolerant Fuel 3

[2D16] R&D of advanced stainless steels for BWR fuel claddings (3)

(7) Evaluation of irradiation behavior

*Naoyuki Hashimoto¹, Kodai Toyota¹, Yixiang Tang¹, Kan Sakamoto², Shinichiro Yamashita³ (1. Faculty of Engineering, Hokkaido University, 2. Nippon Nuclear Fuel Development Co., 3. Japan Atomic Energy Agency )

Keywords:Fuel , BWR, ODS, Mechanical Property

Advanced stainless steels for BWR fuel claddings has been developed as one of accident tolerant fuels. In this study, the relationship between microstructural evaluation and mechanical property of neutron- or ion-irradiated Fe-Cr-Al ODS will be reported.