2019年秋の大会

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V. 核燃料サイクルと材料 » 502-1 原子炉材料,環境劣化,照射効果,評価・分析技術

[3H10-12] ODS鋼

2019年9月13日(金) 14:45 〜 15:35 H会場 (共通教育棟 2F B21)

座長:山下 真一郎(JAEA)

15:00 〜 15:15

[3H11] Phase stability under ion-irradiation in ODS ferritic steels strengthened by different sorts of oxide particles

*Song Peng1、Yabuuchi Kiyohiro1、Kimura Akihiko1 (1. Kyoto Univ.)

キーワード:Phase stability、Oxide particle、ODS steels、Ion irradiation

Considering the difference in chemical compositions and structures of the dominant oxide particles (Y, X, O, X=Ti, Al or Zr) in ODS steels, we aimed to investigate their stability inside steels by means of ion irradiations. Three ODS ferritic steels with Y, Ti co-addition, Y, Ti, Al co-addition, Y, Ti, Al and Zr co-addition, respectively, were irradiated with 6.4 MeV Fe3+ at 200 ºC up to the nominal damage levels of 10 dpa. Post-irradiation observations on radiation defects and nano-sized oxide particles were conducted by using transmission electron microscope (TEM). After the irradiation, both the averaged sizes and number densities of oxide particles in the three steels decreased continuously with the local damage level increasing.