2022 Fall Meeting

Presentation information

Oral presentation

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

[3H01-06] Irradiation Behavior

Fri. Sep 9, 2022 9:30 AM - 11:00 AM Room H (E1 Bildg.3F No.33)

Chair:Kazutoshi Tokunaga(Kyushu Univ.)

10:15 AM - 10:30 AM

[3H04] TEMPERATURE DEPENDENCE ON D RETENTION FOR DAMAGED W-10%RE ALLOY

*Yasuhisa Oya1, Shiori Hirata1, nao Inozume1, Naoaki Yoshida2, Tatsuya Hinoki3, Kiyohiro Yabuuchi3 (1. Shizuoka Univ., 2. Kyushu Univ., 3. Kyoto Univ.)

Keywords:Tungsten-rhenium alloy, Hydrogen isotope behavior, Irradiation damages, Irradiation temperature dependence

In fusion reactor, W will be transmuted by 14MeV neutrons to rhenium to form W-Re alloys. Therefore, hydrogen isotope retention behavior for W-Re alloys was studied as a function of irradiation temperature.The polycrystalline W-10%Re samples was irradiated by 6.4 MeV Fe3+ at room temperature to 1173 K with 1 dpa by DuET. Then, 1.0 keV D2+ irradiation was performed. Thereafter, TDS measurement was performed up to 1173 K. The D desorption was found at 450 K, 600 K and 850 K for W-10%Re irradiated at R.T.. However, no D desorption at higher temperature side, namely 600 K and 850 K, was found for W-10%Re irradiated above 573 K, indicating that the defects in W-10%Re were recovered by annealing.