2024 Annual Meeting

Presentation information

Oral presentation

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

[2G11-16] Functional Material

Wed. Mar 27, 2024 2:45 PM - 4:20 PM Room G (21Bildg.3F 21-317)

Chair:Naoko Ashikawa(Kyoto Fusioneering)

3:15 PM - 3:30 PM

[2G13] Gold-ion irradiation effects on electrical properties and deuterium permeation behavior to zirconium oxide coating

*Heizo Muramatsu1, Kento Shirota1, Yuka Shimizu1, Khiem Do Duy1, Teruya Tanaka2, Takaumi Chikada1 (1. Shizuoka Univ., 2. NIFS)

Keywords:tritium, permeation, coating, irradiation, electrical properties

Ceramic coatings have been investigated to mitigate tritium permeation and MHD pressure drop in liquid metal fusion blankets. and zirconium oxide coatings showed good deuterium permeation reduction, compatibility with liquid lithium-lead, and electric insulation. On the other hand, due to a high energy neutron irradiation environment in the blanket, the evaluation of irradiation effects was important. In this study, we conducted Au-ion irradiation for the coatings because Au ion has a higher ratio of electron-to-nuclear stopping power, which is able to simulate neutron irradiation rather than other ions. In this presentation, the deuterium permeation behavior and electrochemical properties of the zirconium oxide coatings irradiated by Au ions will be discussed.

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