2019 Fall Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[3L01-05] Fusion Reactor Materials 1

Fri. Sep 13, 2019 9:30 AM - 10:55 AM Room L (Common Education Bildg. 2F E22)

Chair:Akira Hasegawa(Tohoku Univ.)

10:15 AM - 10:30 AM

[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.)

Keywords: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.