[2O17-23] Fusion Reactor Materials (Divertor Material, Tungsten)

[2O23] Helium retention behavior in high-temperature simultaneous He-H implanted tungsten

*Qilai Zhou¹, Keisuke Azuma², Akihiro Togari², Miyuki Yajima³, Masayuki Tokitani³, Suguru Masuzaki³, Naoaki Yoshida⁴, Yuji Hatano⁵, Takumi Chikada¹, Yasuhisa Oya¹ (1. Faculty of Science, Shizuoka Univ., 2. Graduate School of Science, Shizuoka Univ., 3. National Inst. for Fusion Science, 4. RIAM, Kyushu Univ., 5. Hydrogen Isotope Res. Cen., Univ. of Toyama)

Keywords:Helium retention, High temperature, Simultaneous implantation of helium and hydrogen isotope, He bubbles

Tungsten (W) is the candidate for plasma facing materials in the future fusion reactor. In this study, W was irradiated simultaneously by He⁺-H₂⁺ at high-temperature. TDS result and TEM observation showed that the formation of He bubbles was depressed by 1.0 H₂⁺. With the increase of irradiation temperature, the effect of H was decreased.