2017 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[2J10-14] Fuel Cladding Tube 2

Tue. Mar 28, 2017 4:10 PM - 5:40 PM Room J (16-305 Building No.16)

Chair: Yoshitaka Matsukawa (Tohoku Univ.)

4:40 PM - 4:55 PM

[2J12] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(8)a/a¢ phase separation effects (Evaluation summary)

Akihiko Kimura1, *Kiyohiro Yabuuchi1, Tadahiko Torimaru2, Shigeharu Ukai3, Naoko Oono3, Takeji Kaito4, Shigenari Hayashi5 (1. IAE, Kyoto University, 2. NFD, 3. Hokkaido University, 4. JAEA, 5. TIT)

Keywords:Accident tolerant fuel cladding

Thermal aging (475℃, 10,000hr) and ion-irradiation (475℃, 8dpa) effects were investigated for FeCrAl-ODS ferritic steels. Hardness, tensile tests and impact tests were crarried out for long term aged specimens. The effects of phase separation of Fe/Cr was invesitated and it was cleared that the age-hardening was due to the phase separation. The ion-irradiation resulted in no phase separation in this irradiation conditions. Lifeime of the candidate materials is evauated on the basis of the results of aging and ion-irradiation experiments.