2017 Fall Meeting

Presentation information

Oral presentation

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

[3O01-05] Fusion Reactor Materials (SiC, Coating Material, Molten Salt)

Fri. Sep 15, 2017 9:30 AM - 10:50 AM Room O (Seminar room 1- Frontier Research in Applied Sciences Building)

Chair:Yuji Hatano (Univ. of Toyama)

10:00 AM - 10:15 AM

[3O03] Lithium-lead compatibility of tritium permeation barrier coatings fabricated by a liquid phase method and their deuterium permeation behavior after lithium-lead exposure

*Moeki Matsunaga1, Seira Horikoshi1, Jumpei Mochizuki1, Hikari Fujita2, Yoshimitsu Hishinuma3, Kanetsugu Isobe4, Takumi Hayashi4, Yasuhisa Oya1, Takayuki Terai2, Takumi Chikada1 (1. Shizuoka Univ., 2. Univ. of Tokyo, 3. NIFS, 4. QST)

Keywords:Lithium-lead, Corrosion, Tritium, Permeation, Ceramic coating

Er2O3, Y2O3 and ZrO2 coatings were fabricated on reduced activation ferritic/martensitic steel F82H substrates by metal organic decomposition which is a promising coating technique for plant-scale fabrication with a large reduction of hydrogen isotope permeation. Static immersion tests for the coatings in liquid lithium-lead at 400-600 ºC for 100-500 h and gas-driven deuterium permeation measurements at 300-600 ºC for the immersed samples were carried out to investigate lithium-lead compatibility.