2024 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-4 Reactor Component Technology, First Wall, Divertor, Magnet

[3G10-15] Fusion Reactor Components

Thu. Mar 28, 2024 2:45 PM - 4:20 PM Room G (21Bildg.3F 21-317)

Chair:Masatosh Kondo(Tokyo Tech)

3:00 PM - 3:15 PM

[3G11] Effects of irradiation defects on HD mixed plasma driven permeation for tungsten-rhenium alloy

*Yuzuka Hoshino1, Ashikawa Naoko2, Toyama Takeshi3, Shimada Masashi4, Kolasinski Robert 5, Yasuhisa Oya1 (1. Shizuoka Univ., 2. KF, 3. Tohoku Univ, 4. INL, 5. SNL)

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 candidate materials 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 the irradiation defects by neutron irradiation would work as a permeation path for solute hydrogen isotope from HD plasma permeation fluxes.

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