2018 Annual Meeting

Presentation information

Oral presentation

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

[2C14-18] Behaviors of Hydrogen Isotopes in Fusion Materials

Tue. Mar 27, 2018 4:40 PM - 6:00 PM Room C (R1-211 -R1 Building)

Chair: Yuji Hatano (Univ. of Toyama)

4:40 PM - 4:55 PM

[2C14] Removal of retained tritium retained in tungsten-carbon mixed material deposits by deuterium gas exposure

*Akihiro Togari1, Keisuke Azuma1, Qilai Zhou2, Yuji Hatano3, Miyuki Yajima4, Masayuki Tokitani4, Suguru Masuzaki4, Takumi Chikada5, Yasuhisa Oya5 (1. Grad. School of Sci. and Tech. Shizuoka Univ., 2. Fac. of Sci. Shizuoka Univ., 3. HRC, Univ. of Toyama, 4. NIFS, 5. Dept. of Sci, Shizuoka Univ.)

Keywords:Tungsten, Tritium retention, Deuterium exposure, Hydrogen isotope exchange

Hydrogen isotope exchange is suggested as a retained tritium removal method. In this study, tritium and deuterium gas exposure for W-deposited C-W mixture layer was performed at various temperatures and pressures. After that, thermal desorption spectroscopy measurement was performed to evaluate the retention behavior of each hydrogen isotope and tritium removal effect.