2023 Fall Meeting

Presentation information

Oral presentation

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

[2L08-12] Structural Materials for Nuclear Fusion Reactors 1

Thu. Sep 7, 2023 2:45 PM - 4:05 PM Room L (ES Bildg. 3F ES033)

Chair:Akira Hasegawa(Tohoku Univ.)

3:00 PM - 3:15 PM

[2L09] Effects of irradiation defects on HD mixed plasma driven permeation for tungsten-rhenium alloy

*Yuzuka Hoshino1, Naoko Ashikawa2,3, Tatsuya Hinoki4, Kiyohiro Yabuuti4, Yasuhisa Oya1 (1. Shizuoka Univ., 2. NIFS, 3. SOKENDAI, 4. Kyoto Univ.)

Keywords:Tungsten, Rhenium, HD 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 material for plasma facing components (PFMs) in the fusion reactors. 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. It was suggested that formation of He bubbles by He++ Fe3+ irradiation would work as a diffusion barrier from HD plasma permeation fluxes and calculated diffusion coefficients.

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