2023 Annual Meeting

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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)

3:00 PM - 3:15 PM

[1A08] Effects of Mo or Zr Addition on Plasma Irradiation Resistance of W-Y2O3 Alloy

*Qiu Xu1, Mitsutaka Miyamoto2, Masayuki Tokitani3, Koichi Sato4 (1. Institute for Integrated Radiation and Nuclear Science, Kyoto University, 2. Shimane University, 3. National Institute for Fusion Science, 4. Kagoshima University)

Keywords:tungsten alloys, plasma, helium, deuterium

In the present study, Mo or Zr added W-Y2O3 alloys were irradiated with helium or deuterium plasma to investigate the effects of Mo or Zr addition on the surface damage of tungsten alloys.