Presentation Information
[2I10]Evaluation of irradiation defect and deuterium retention behavior for K-doped W under high temperature conditions
*kenshiro miura1, Yuzuka Hoshino1, Asahi Sanfukuji1, Naoaki Yoshida2, Yasuhisa Oya1 (1. Shizuoka Univ., 2. Kyusyu Univ.)
Keywords:
Potassium doped tungsten,Hydrogen isotope retention behavior,Irradiation defects
Tungsten (W) is one of candidate materials for PFMs in the D-T fusion reactors, where W will be exposed to energetic fuel particles and neutrons, leading to the enhancement of hydrogen isotope retention. Previous reports showed K-doped W was suppressed the embrittlement of W. In this study, for W and K-doped W with irradiation defects introduced by Fe2+ irradiation at room and high temperature. Thereafter, the D2+ ion implantation was performed, and D retention was evaluated by TDS. The size and density of defects was observed by PAS. The D desorption for W-K at the lower temperature stage was lower than that for W, indicating many small defects were introduced in W-K and the number of large defects was reduced.