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)

3:30 PM - 3:45 PM

[2G14] Deuterium permeation measurements for zirconium oxide coating under exposure to various ceramic breeder pebbles

*Takumi Chikada1, Wataru Matsuura1, Julia Leys2, Khime Duy Do1 (1. Shizuoka Univ., 2. KIT)

Keywords:Tritium, Permeation, Coating, Corrosion, Solid breeder

Deuterium permeation experiments have been conducted for zirconium oxide coatings under exposure to various solid tritium breeder pebbles in order to assess the integrity of the coatings in fusion reactor solid breeder blankets.

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