2019年春の年会

講演情報

一般セッション

VI. 核融合工学 » 601-2 核融合炉材料工学(炉材料,ブランケット,照射挙動)

[1O01-07] タングステン(水素同位体挙動)

2019年3月20日(水) 10:00 〜 11:55 O会場 (共通教育棟2号館 4F 46番)

座長:外山 健(東北大)

10:45 〜 11:00

[1O04] Impact of helium irradiation and damage introduction on hydrogen isotope retention behaviors in tungsten

*Fei Sun1, Akihiro Togari2, Moeko Nakata2, Mingzhong Zhao2, Sosuke Kondo3, Tatsuya Hinoki4, Yasuhisa Oya2 (1. Faculty of Science, Shizuoka University, 2. Graduate School of Science and Technology, Shizuoka University, 3. Institute for Materials Research, Tohoku University, 4. Institute of Advanced Energy, Kyoto University)

キーワード:Helium, hydrogen isotope, irradiation damages, simulation, tungsten, fusion

Impact of helium irradiation and damage introduction on hydrogen isotope retention behaviors was studied using simultaneous He+ and Fe3+ irradiation. The additional D2+ implantation was performed, and D retention was evaluated by TDS. Based on these experimental results, the model of hydrogen isotope diffusion and trapping across helium bubble layer in tungsten was established. Good agreement can be achieved by comparing simulations based on the established model to the experimental results, indicating that D desorption behavior can be reasonably explained.