2016 Annual Meeting

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Oral Presentation

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

[1H14-21] ODS Structure materials Ni alloys

Sat. Mar 26, 2016 4:05 PM - 6:15 PM Room H (Lecture Rooms B B204)

Chair: Naoyuki Hashimoto (Hokkaido Univ.)

4:50 PM - 5:05 PM

[1H17] R&D of fuel cladding of ODS ferritic steel for maintaining fuel integrity at accidental high temperature condition (2)

(4)Evaluation of Ion Irradiation Effect

＊Kiyohiro Yabuuchi1, Wentuo Han1, Akihiko Kimura1, Takeji Kaito3, Tadahiko Torimaru4, Shigenari Hayashi5, Naoko Oono2, Shigeharu Ukai2 (1.IAE, Kyoto Univ., 2.Hokkaido Univ., 3.JAEA, 4.NFD, 5.Institute of Tokyo Univ.)

Keywords:fuel claddings, ODS steels, irradiation effect

事故耐性用燃料被覆管の開発の一環として、高Cr-ODS鋼の照射影響について調べた結果を報告する。