2023年秋の大会

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VI. 核融合工学 » 601-2 核融合炉材料工学(炉材料,ブランケット,照射挙動)

[2L08-12] 核融合炉構造材料1

2023年9月7日(木) 14:45 〜 16:05 L会場 (ES総合館3F ES033)

座長:長谷川 晃(東北大)

15:30 〜 15:45

[2L11] Ion irradiation effects on the 12Cr ODS steel after a novel recrystallization process

*Jingjie Shen1, Takeo Muroga1, Kiyohiro Yabuuchi2, Sho Kano3, Hiroaki Abe3 (1. NIFS, 2. Kyoto Univ., 3. UTokyo)

キーワード:ODS steel, Ion irradiation, irradiation defects, Hardening

A multi-directional thermomechanical process was applied to get recrystallization and thus improve the ductility of oxide dispersion strengthened (ODS) ferritic steel. In this study, it is to investigate the microstructural evolution and hardness changes of the recrystallized 12Cr ODS steel upon ion irradiation. Ion irradiation experiments were carried out at 973 K using single beam (6.4 MeV Fe3+) and dual beam (6.4 MeV Fe3+ and 1 MeV He+). Irradiation dose was estimated at about 10.5 dpa at the peak damage. After irradiation, the nanoindentation harness tests were conducted, and microstructure was characterized by TEM. Results showed that irradiation defects such as helium bubbles were observed, however, the irradiation hardening was not obvious, suggesting helium bubbles did not evidently induce hardening.