Tritium distribution measurement of JET Mk IISRP divertor tiles

T. Tanabe (Corresponding Author), K. Sugiyama, T. Renvall, J. Likonen, L. Penttinen, E. Vainonen-Ahlgren, J.P. Coad

    Research output: Contribution to journalArticleScientificpeer-review

    10 Citations (Scopus)

    Abstract

    Tritium surface distribution on the JET Mark II Septum Replacement Plate (Mk II SRP) divertor tiles was measured by imaging plate technique. It was observed that areal tritium concentration was higher at the entrance of inner/outer pumping slots (so called ‘shadowed area’).
    The tritium distribution profiles were similar to those obtained in the Mk IIA divertor which was exposed to a series of D–T plasma operation (DTE1). Tritium concentration of the plasma facing surface was lower compared to that of the shadowed area. Particularly, it was very low at the outer divertor surface.
    The inner divertor surface also showed low level of tritium retention, though it was covered by the thick carbon deposition on that. This could be caused by tritium release due to the temperature rise when the inner strike point was on the tiles.
    On the plasma shadowed area like tile gaps, high tritium retention owing to the codeposition was observed.
    Original languageEnglish
    Pages (from-to)960-965
    JournalJournal of Nuclear Materials
    Volume363-365
    DOIs
    Publication statusPublished - 2007
    MoE publication typeA1 Journal article-refereed
    Event17th International Conference on Plasma Surface Interactions in Controlled Fusion Devices - Hefei, China
    Duration: 22 May 200626 May 2006

    Keywords

    • tritium
    • JET
    • divertor
    • carbon-based materials
    • hydrogen retention
    • ITER
    • fusion energy
    • plasma
    • tungsten

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