2019 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[1O01-07] Tungsten Materials (Behavior of Hydrogen Isotope)

Wed. Mar 20, 2019 10:00 AM - 11:55 AM Room O (Common Education Bildg. 2 4F No.46)

Chair:Takeshi Toyama(Tohoku Univ.)

10:45 AM - 11:00 AM

[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)

Keywords: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.