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.)

10:15 AM - 10:30 AM

[1O02] Evaluation of surface and bulk defect distribution influence on deuterium retention in damaged tungsten

*Takuro Wada1, Akihiro Togari2, moeko nakata2, Mingzhong Zhao2, Fei Sun1, Yuji Hatano3, Yasuhisa Oya1 (1. Faculty of Science, Shizuoka University, 2. Graduate School of Science and Technology, Shizuoka University, 3. Hydrogen Isotope Research Center, University of Toyama)

Keywords:Tungsten, hydrogen ion implantation, heavy ion implantation, deuterium retention behavior, Thermal Desorption Spectroscopy

To evaluate the deuterium (D) retention behavior in tungsten (W) with various damage distributions, Fe ions and H ions were implanted into tungsten with various damage concentrations. Thereafter, 3.0 keV D2+ implantation and thermal desorption spectroscopy were performed to evaluate the D retention behavior. The D retention in W was affected by the damage range.