2023 Fall Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-3 Tritium Science and Technology (Fuel Recovery and Refining, Measurement, Iisotope Effect, Safe Handling)

[1L15-18] Tritium in DEMO/LHD/JET

Wed. Sep 6, 2023 4:40 PM - 5:45 PM Room L (ES Bildg. 3F ES033)

Chair:Teppei Otsuka(Kindai Univ.)

5:10 PM - 5:25 PM

[1L17] Scenario of tritium decontamination on plasma-facing components in Fusion DEMO

*Naoko Ashikawa1,2, Yuji Torikai3, Kazuaki Kasai3, Yoji Someya4, Akira Taguchi5, Kiyohiro Yabuuchi6 (1. NIFS, 2. SOKENDAI, 3. Ibaraki Univ., 4. QST, 5. U. of Toyama, 6. Kyoto Univ.)

Keywords:Tritium decontamination, Fusion DEMO, Operational Scenario

The tritium (T) decontamination scenario before the beginning of periodic maintenance is critical for obtaining the constructional and operational licenses of DEMO. This study classifies the available methods for tritium decontamination in DEMO reactors into three categories, and provides examples based on the candidate parameters and each operational phase of DEMO. Laboratory scale experiments demonstrated that the presence of moisture in working gas significantly enhanced T desorption. Moreover, a part of T in W with radiation damage could be desorbed in the temperature range near 623 K by the isothermal desorption method.

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