2023 Annual Meeting

Presentation information

Oral presentation

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

[1A07-11] Divertor and Superconducting Materials

Mon. Mar 13, 2023 2:45 PM - 4:10 PM Room A (11 Bildg.1F 1101)

Chair:satoshi konishi(Kyoto Fusioneering)

3:30 PM - 3:45 PM

[1A10] Role of nuclear transmuted Re on tungsten by HD mixed plasma irradiation Hydrogen isotope permeation behavior for W-Re alloy by HD mixed plasma exposure

*Yuzuka Hoshino1, Naoko Ashikawa2, Yasuhisa Oya1 (1. Shizuoka Univ., 2. NIFS)

Keywords:Tungsten, Rhenium, Mixed plasma irradiation

In the fusion reactor, energy is obtained using a fusion reaction of deuterium (D) and tritium (T). Tungsten (W) is one of the candidates for plasma facing materials (PMFs) in the fusion reactors due to its higher melting point and lower sputtering yield. W will be exposed to high flux D and T including helium (He) ash during the operation. In addition, 14MeV neutron, that produced by nuclear fusion reaction of D and T, will be irradiated into W, leading to the transmutation of Re in W. Therefore, the evaluation of hydrogen isotope permeation behavior for W-Re alloy are important. In the presentation, we will discuss the hydrogen isotope effect of W-10%Re by HD mixed plasma.