2021 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[1K01-04] Irradiation Effect

Wed. Mar 17, 2021 10:00 AM - 11:10 AM Room K (Zoom room 11)

Chair: Hirotatsu Kishimoto (Muroran IT)

10:15 AM - 10:30 AM

[1K02] Swelling resistance of ODS steel for fuel cladding tube of fast reactor

*Takashi TANNO1, Hiroshi OKA1,2, Yasuhide YANO1, Satoshi OHTSUKA1, Takeji KAITO1 (1. JAEA, 2. Current: Hokkaido Univ.)

Keywords:ODS steel, fast reactor, fuel cladding tube, swelling

Fe + He dual ions beam irradiation to ODS steels and other materials which are developed as the candidates for fuel cladding tubes of fast reactor was carried out in order to evaluate their swelling resistance. Austenitic steels and tempered martensitic steels, which are not ODS, were swelled due to coarse voids formation by the irradiation. On the other hand, the swelling of ODS steels was much smaller than the others after irradiation up to 95 dpa. The fact shows that the fine dispersed oxide in ODS steels can suppress the swelling strongly.