2017 Annual Meeting

Presentation information

Oral presentation

V. Fusion Energy Engineering » 501-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[2B01-05] Hydrogen Isotope Behavior

Tue. Mar 28, 2017 9:30 AM - 10:50 AM Room B (16-102 Building No.16)

Chair: Ryuta Kasada (Kyoto Univ.)

10:00 AM - 10:15 AM

[2B03] The effect of deuterium plasma implantation on deuterium retention behavior for heavy ion implanted W.

*Keisuke Azuma1, Yuki Uemura1, Shodai Sakurada1, Hiroe Fujita1, Qilai Zhou2, Naoaki Yoshida3, Takeshi Toyama4, Sosuke Kondo5, Takumi Chikada1, Yasuhisa Oya1 (1. Graduate School of Science & Technology, Shizuoka Univ., 2. Faculty of science, Shizuoka Univ., 3. Insitute for Applied Mechanics, Kyushu Univ., 4. Institute for Materials Research, Tohoku Univ., 5. Institute of Advanced Energy, Kyoto Univ.)

Keywords:Tungsten, Plasma implantation, Heavy ion implantation, Deuterium retention behavior

Tungsten (W) is considered to be a candidate for plasma facing materials (PFMs) in fusion reactor. It will be exposed to energetic neutron escaped from plasma during the plasma operation. In that time, implantation defects which trap hydrogen isotope, will be introduced. In our previous study, D retention behavior in damaged W by iron ion implantation to simulate the implantation defect was estimated by D2+ implantation. In the actual fusion reactor, W will be exposed to low energy and high flux hydrogen plasma. Therefore, hydrogen isotope retention behavior in plasma irradiated W is expected to be quite different from that of ion implanted W. In this study, D retention behavior for Fe2+ damaged W with D plasma was compared to that with D2+ ion implantation. From this experiment, it was suggested that D was trapped by the defect in order from surface to bulk in comparison to D2+ ion implanted W. The HIDT simulation is applied to estimate of trapping energy of hydrogen isotopes in damaged W and D plasma irradiation effect will be discussed.