2022 Annual Meeting

Presentation information

Oral presentation

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

[2L01-04] Plasma-material Interaction in Fusion Reactors

Thu. Mar 17, 2022 9:45 AM - 11:00 AM Room L

Chair: Takuya Nagasaka (NIFS)

10:15 AM - 10:30 AM

[2L03] Hydogen isotope mixed plasma driven permeation for neutron damaged tungsten

*Yasuhisa Oya1, Ashizawa Kyosuke1, Shiori Hirata1, Naoko Ashikawa2, Yoji Someya3, Yuji Hatano4, Masashi Shimada5, Chase N. Taylor5, Robert Kolasinski6 (1. Shizuoka University, 2. NIFS, 3. QST, 4. University of Toyama, 5. INL, 6. SNL)

Keywords:Tungsten, Hydrogen isotope, PDP, Neutron irradiation

H and D mixed plasma driven permeation behavior for neutorn damaged tungsten(W) was studied at PDP device in Shizuoka University. The H and D retentions for undamaged or damgaed W after PDP experiment was also evaluated by TDS. It was found that H and D permeation flux was increased at the temperature less than 800 K for neutron damaged W. H/D permeation ratio for undamaged W was increased at the temperature less than 850 K, but that for neutron damaged W was almost constant. It was indicatd that H and D permeation behavior is influenced by the introduction of irradiation damages.