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.)

11:30 AM - 11:45 AM

[1O07] Hydrogen isotope retention in W-based high entropy alloys

*Heun Tae Lee1, Ho Jin Ryu2, Ryuta Kasada3, Kenzo Ibano1, Yoshio Ueda1 (1. Graduate School of Engineering, Osaka University, 2. Korea Advanced Institute of Science and Technology, 3. Institute of Materials Research, Tohoku University)

Keywords:High entropy alloys, Hydrogen isotope retention, Mechanical properties

Hydrogen isotope retention in W-based high entropy alloys (WTaCrV and WTaCrVTi) was studied for the purpose of evaluating such alloys as possible plasma facing material in fusion devices. Retention increases by three orders of magnitude in comparison to pure W following ion irradiation. Changes in mechanical property and surface morphology will also be presented.