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Determination of tritium inventory in carbon divertor tiles used in deuterium plasma experiment by induction heating method

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Názov: Determination of tritium inventory in carbon divertor tiles used in deuterium plasma experiment by induction heating method
Autori: Masahiro Tanaka, Hiromi Kato, Naoyuki Suzuki, Hiroki Chimura, Hiroaki Yonezu, Suguru Masuzaki
Zdroj: Nuclear Materials and Energy, Vol 42, Iss , Pp 101876- (2025)
Informácie o vydavateľovi: Elsevier, 2025.
Rok vydania: 2025
Zbierka: LCC:Nuclear engineering. Atomic power
Predmety: Tritium inventory, Carbon divertor tile, Tritium chemical forms, Deuterium plasma experiment, Thermal desorption, Induction heating method, Nuclear engineering. Atomic power, TK9001-9401
Popis: The tritium inventory of the plasma-facing materials in a Large Helical Device (LHD) was analyzed using a thermal desorption system. In this study, we developed an induction heating system for the thermal desorption of tritium from carbon divertor tiles, which has several advantages, including a rapid temperature rise, internal heating via eddy currents, and heating with the original size and shape of the carbon tile. The apparatus was capable of heating a carbon divertor tile to a temperature greater than 1373 K over 20 min. Following a 12-h heating period at 1423 K, the tritium release rate from the carbon tile was 99.7 %. The chemical form of the tritium released from the divertor tiles was approximately 80 % molecular hydrogen, with the remaining tritium in the form of water vapor. The results of the tritium analysis of the divertor tiles suggest that the tritium distribution in the divertor region is not uniform, and that the flux varies from location to location in the LHD. To improve the accuracy of the tritium inventory analysis in an LHD vacuum vessel, it is essential to conduct a tritium inventory analysis of other plasma-facing materials.
Druh dokumentu: article
Popis súboru: electronic resource
Jazyk: English
ISSN: 2352-1791
Relation: http://www.sciencedirect.com/science/article/pii/S235217912500016X; https://doaj.org/toc/2352-1791
DOI: 10.1016/j.nme.2025.101876
Prístupová URL adresa: https://doaj.org/article/536a1e9027264f80885b02d5ed26bd2a
Prístupové číslo: edsdoj.536a1e9027264f80885b02d5ed26bd2a
Databáza: Directory of Open Access Journals
Popis
Abstrakt:The tritium inventory of the plasma-facing materials in a Large Helical Device (LHD) was analyzed using a thermal desorption system. In this study, we developed an induction heating system for the thermal desorption of tritium from carbon divertor tiles, which has several advantages, including a rapid temperature rise, internal heating via eddy currents, and heating with the original size and shape of the carbon tile. The apparatus was capable of heating a carbon divertor tile to a temperature greater than 1373 K over 20 min. Following a 12-h heating period at 1423 K, the tritium release rate from the carbon tile was 99.7 %. The chemical form of the tritium released from the divertor tiles was approximately 80 % molecular hydrogen, with the remaining tritium in the form of water vapor. The results of the tritium analysis of the divertor tiles suggest that the tritium distribution in the divertor region is not uniform, and that the flux varies from location to location in the LHD. To improve the accuracy of the tritium inventory analysis in an LHD vacuum vessel, it is essential to conduct a tritium inventory analysis of other plasma-facing materials.
ISSN:23521791
DOI:10.1016/j.nme.2025.101876