2017 Annual Meeting

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V. Fusion Energy Engineering » 501-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[2B01-05] Hydrogen Isotope Behavior

Tue. Mar 28, 2017 9:30 AM - 10:50 AM Room B (16-102 Building No.16)

Chair: Ryuta Kasada (Kyoto Univ.)

9:30 AM - 9:45 AM

[2B01] Hydrogen isotope permeation behavior in reduced activation ferritic steel F82H under γ-ray irradiation

*Hikari Fujita1, Jumpei Mochizuki2, Seira Horikoshi2, Moeki Matsunaga1, Yasuhisa Oya1,2, Takumi Chikada1,2 (1. Fac. Sci., Shizuoka Univ., 2. Grad. Sch. Integrated Sci. Technol., Shizuoka Univ.,)

Keywords:Tritium, Permeation, Reduced activation ferritic steel, F82H, γ-ray, Irradiation

As a study on tritium permeation in a fusion reactor blanket, deuterium permeation measurements have been performed with reduced activation ferritic steel F82H under γ-ray irradiation to elucidate γ-ray irradiation effect on hydrogen isotope permeation through structural materials.