2024 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)/601-3 Tritium Science and Technology (Fuel Recovery and Refining, Measurement, Iisotope Effect, Safe Handling)

[2G17-22] Tungsten

Wed. Mar 27, 2024 4:20 PM - 5:55 PM Room G (21Bildg.3F 21-317)

Chair:Takumi Chikada(Shizuoka Univ.)

4:35 PM - 4:50 PM

[2G18] Quantitative analytical method of tritium in tungsten

(2)Tritium analysis on tungsten samples with irradiation damage

*Naoko Ashikawa1,2, Kazuaki Kasai3, Yuji Torikai3, Rion Nishida3, Akira Taguchi4, Kiyohiro Yabuuchi5, Yoji Someya6 (1. NIFS, 2. SOKENDAI, 3. Ibaraki Univ., 4. Univ. of Toyama, 5. Kyoto Univ., 6. QST)

Keywords:Quantitative tritium analysis, Tungsten, plasma exposure, Iron ion irradiation

Understanding tritium (T) retention and decontamination is critical for obtaining the construction and operational licenses of the fusion plant. For the demonstration of the operational condition of materials with is located in the plasma vacuum vessel, plasma exposure, and iron (Fe) irradiation are treated on the W. And the W specimens were exposed to the T gas. Visualized tritium contamination, including depth information on Fe irradiated W with the chemical etching method, is shown.

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