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.)

4:50 PM - 5:05 PM

[2G19] Quantitative analytical method of tritium in tungsten

(3)Quantitative tritium analysis in JET tiles

*Rion Nishida1, Kazuaki Kasai1, Yuuji Torikai1, Naoko Asikawa2,3, Hirohumi Nakamura4, Yutaka Sugimoto4, Suguru Masuzaki2,3, Miyuki Yajima2,3, Anna Widdowson5, Marek Rubel6 (1. Ibaraki Univ., 2. NIFS, 3. SOKENDAI, 4. QST, 5. UKAEA, 6. KTH Royal Institute of Technology)

Keywords:Quantitative tritium analysis, Tungsten, Chemical etching, JET divertor tiles

In order to evaluate tritium retention in fusion reactor materials, a new chemical etching method was used to analyze tungsten (W) divertor tiles of the 1st JET ITER-like wall experiments.The W surface containing tritium is dissolved by a mixture of sodium hydroxide solution and hydrogen peroxide solution. A liquid scintillation counter measures tritium in a collected solution, enabling quantitative tritium measurement in the dissolved liquid .Dissolved surfaces on the W sample were selected by masking with plastic tape, and tritium amounts on different surfaces of the sample were compared.Multiple chemical etchings of approximately 1 μm each were performed on W samples. And tritium amounts of different depths from the top surface are confirmed as quantitative measurements.

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