2021 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[3L01-04] Chemical Compatibility of Materials 1

Fri. Mar 19, 2021 9:30 AM - 10:35 AM Room L (Zoom room 12)

Chair: Teruya Tanaka (NIFS)

10:15 AM - 10:30 AM

[3L04] Compatibility test of tritium permeation barrier coatings with pressurized water

*Takumi Chikada1, Motoki Nakajima2, Akiyoshi Suzuki1, Teppei Otsuka3, Masanori Hara4, Takashi Nozawa2 (1. Shizuoka Univ., 2. QST, 3. Kindai Univ., 4. Univ. of Toyama)

Keywords:Tritium, Permeation, Coating, Pressurized water, Corrosion

Tritium permeation through structural materials in fusion reactor blankets is a serious issue in most blanket concepts, and tritium permeation barrier technology using coatings has been developed. However, the number of reports addressing the stability of the coating under blanket environments is limited. In this presentation, compatibility of tritium permeation barrier coatings under a water-cooled pebble-bed blanket environment is reported through exposure tests for various coatings to pressurized water.