[2B01-05] Hydrogen Isotope Behavior

[2B02] Removal of retained tritium in tungsten by deuterium gas exposure

*Akihiro Togari¹, Yuki Uemura², Shodai Sakurada², Hiroe Fujita², Yuji Hatano³, Miyuki Yajima⁴, Masayuki Tokitani⁴, Suguru Masuzaki⁴, Takumi Chikada⁵, Yasuhisa Oya⁵ (1. Fac. Sci., Shizuoka Univ., 2. Grad. Sch. Integrated Sci. Eng., Shizuoka Univ., 3. HRC, Univ. Toyama, 4. NIFS, 5. Coll. Sci., Acad. Inst., Shizuoka Univ.)

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

Tritium inventory in tungsten (W), one of the candidates for plasma facing materials, is an important issue for fuel efficiency and radioactive safety in fusion reactors. Hydrogen isotope exchange is suggested as a retained tritium removal method. In this study, tritium gas exposure for W-deposited C-W mixture layer was performed and the sample was exposed to deuterium gas at various temperatures. After that, thermal desorption spectroscopy measurement was performed to evaluate the retention behavior of each hydrogen isotope and tritium removal effect. From the results, it is suggested that isotope exchange reaction is enhanced under high temperature.