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.)

3:45 PM - 4:00 PM

[1B12] Corrosion behavior of tritium permeation barrier coating in static liquid Li-Pb and post-corrosion deuterium permeation measurement

*Seira Horikoshi1, Moeki Matsunaga1, Jumpei Mochizuki2, Hikari Fujita2, Yasuhisa Oya1,2, Takumi Chikada1,2 (1. Graduated School of Integrated Science and Technology, Shizuoka University, 2. Faculty of Science, Shizuoka University)

Keywords:Lithium-lead, Corrosion, Permeation, Coating, Erbium oxide

To investigate corrosion behavior of tritium permeation barrier coatings, immersion tests in static liquid Li15.7Pb84.3 for 50-1500 h were performed with single Er2O3 layer and Er2O3-Fe coatings. Deuterium permeation measurements for the coating after immersion were also carried out to investigate the influence of the corrosion on tritium permeation behavior.