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.)

2:45 PM - 3:00 PM

[1B08] Study on self-healing type functional interface structures for fusion blanket systems

*Masatoshi KONDO1, Teruya Tanaka2, Yoshimitsu Hishinuma2, Akio Sagara2, Yoshihito Matsumura3, Takeo Muroga2 (1. Tokyo Institute of Technology, Laboratory for Advanced Nuclear Energy, 2. National Institute for Fusion Science, Department of Helical Plasma Research, 3. Tokai university)

Keywords:liquid blanket, tritium permeation barrier, oxidation , corrosion , functional layer

Function sharing type interface structures, which have the functions of tritium permeation barrier and self-healing after damage, have been studied for the development of long-life liquid breeder blanket system of fusion reactors. The chemical stability of Zr based function sharing type interface structure was investigated by means of high temperature oxidation test in air at 773K and liquid metal Pb immersion test at 873K.