Current status and issues on ODS tempered martensitic steel development for performance enhancement of advanced nuclear power system

Otsuka, Satoshi   ; Tanno, Takashi  ; Yano, Yasuhide  ; Fujita, Koji; Shizukawa, Yuta ; Hashidate, Ryuta ; Onizawa, Takashi  ; Kaito, Takeji ; Ito, Chikara   

Implementation of fusion energy system and fast reactor cycle system requires the development of advanced materials resistant to the severe core environment where high-temperature and high-dose neutron irradiation are superposed. A lot of efforts have been made worldwide for research and development of oxide dispersion strengthened (ODS) steels with a variety of specification; Japan Atomic Energy Agency (JAEA) has focused on the development of 9Cr,11Cr-ODS tempered martensitic steel (TMS) for high-burnup fuel cladding tube of sodium-cooled fast reactor (SFR). This paper overviews the current status on 9Cr,11Cr-ODS TMS cladding tube development in JAEA, and discusses the cross-cutting issues in material development for advanced nuclear power systems.