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.)

3:30 PM - 3:45 PM

[1B11] Corrosion behavior of tritium permeation barrier coatings fabricated by a liquid phase method in liquid lithium-lead

*Moeki Matsunaga1, Seira Horikoshi2, Jumpei Mochizuki2, Hikari Fujita1, Yasuhisa Oya1,2, Takayuki Terai3, Kanetsugu Isobe4, Takumi Hayashi4, Takumi Chikada1,2 (1. Fac. Sci., Shizuoka Univ., 2. Grad. Sch., Shizuoka Univ., 3. Sch. Eng., Univ. Tokyo, 4. QST)

Keywords:Lithium-lead, Corrosion, Coating, Erbium oxide, Yttrium oxide, Zirconium oxide

Er2O3, Y2O3 and ZrO2 coatings were fabricated on reduced activation ferritic/martensitic steel substrates by metal organic decomposition which is a promising coating technique for plant-scale fabrication with a large reduction of hydrogen isotope permeation. The static immersion tests for the coatings in liquid lithium-lead at 400-600 0C for 50-200 h were performed to investigate the corrosion behavior.