2017 Annual Meeting

Presentation information

Oral presentation

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

[1B08-14] Permeation and retention characteristics of hydrogen isotopes

Mon. Mar 27, 2017 2:45 PM - 4:40 PM Room B (16-102 Building No.16)

Chair: Bun Tsuchiya (Meijo Univ.)

3:00 PM - 3:15 PM

[1B09] Deuterium permeation behavior and its Fe-ion irradiation effect in yttrium oxide coating prepared by magnetron sputtering

*Takumi Chikada1,2, Jan Engels3, Anne Houben3, Seira Horikoshi2, Jumpei Mochizuki2, Hikari Fujita1, Moeki Matsunaga1, Sosuke Kondo4, Kiyohiro Yabuuchi4, Yasuhisa Oya1,2 (1. Fac. Sci., Shizuoka Univ., 2. FZJ, 3. Grad. Sch. Integrated Sci. Technol., Shizuoka Univ., 4. Kyoto Univ.)

Keywords:Tritium, Permeation, Coating, Yttrium oxide, Irradiation

Microstructural analysis and deuterium permeation measurements for yttrium oxide coatings deposited by magnetron sputtering have been performed as a study on tritium permeation barrier in fusion fuel systems. Irradiation effect on permeation has been also investigated with iron-ion irradiated coatings.