2019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)

[3L01-05] 核融合炉材料1

2019年9月13日(金) 09:30 〜 10:55 L会場 (共通教育棟 2F E22)

座長:長谷川 晃(東北大)

10:15 〜 10:30

[3L04] The effect of coolant temperature on stress corrosion cracking behavior of SUS316L in fusion relevant environments

*Yen-Jui Huang1, Kiyohiro Yabuuchi1, Akihiko Kimura1 (1. Kyoto Univ.)

キーワード:stress corrosion cracking, hydrogen embrittlement, hydrogen-assisted stress corrosion cracking, SSRT

The effect of coolant temperature on the susceptibility of stress corrosion cracking (SCC) of SUS316L wa investigated by means of slow strain rate test (SSRT). Results indicated a temperature dependence with susceptibility peaked around 613K (340oC) at pressurized condition. Further, intergranularly fracture mode was recognized.