Tritium distribution measurement of JET Mk II SRP divertor tiles

T. Tanabe, K. Sugiyama, T. Renvall, Jari Likonen, L. Penttinen, Elizaveta Vainonen-Ahlgren, J.P. Coad

    Research output: Contribution to journalArticleScientificpeer-review

    7 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

    Fingerprint

    septum
    Tritium
    tiles
    Tile
    tritium
    Plasmas
    slots
    entrances
    pumping
    Carbon
    Imaging techniques
    carbon
    profiles

    Keywords

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

    Cite this

    Tanabe, T., Sugiyama, K., Renvall, T., Likonen, J., Penttinen, L., Vainonen-Ahlgren, E., & Coad, J. P. (2007). Tritium distribution measurement of JET Mk II SRP divertor tiles. Journal of Nuclear Materials, 363-365, 960-965. https://doi.org/10.1016/j.jnucmat.2007.01.191
    Tanabe, T. ; Sugiyama, K. ; Renvall, T. ; Likonen, Jari ; Penttinen, L. ; Vainonen-Ahlgren, Elizaveta ; Coad, J.P. / Tritium distribution measurement of JET Mk II SRP divertor tiles. In: Journal of Nuclear Materials. 2007 ; Vol. 363-365. pp. 960-965.
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    title = "Tritium distribution measurement of JET Mk II SRP divertor tiles",
    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.",
    keywords = "tritium, JET, divertor, carbon-based materials, hydrogen retention, ITER, fusion energy, plasma, tungsten",
    author = "T. Tanabe and K. Sugiyama and T. Renvall and Jari Likonen and L. Penttinen and Elizaveta Vainonen-Ahlgren and J.P. Coad",
    year = "2007",
    doi = "10.1016/j.jnucmat.2007.01.191",
    language = "English",
    volume = "363-365",
    pages = "960--965",
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    Tanabe, T, Sugiyama, K, Renvall, T, Likonen, J, Penttinen, L, Vainonen-Ahlgren, E & Coad, JP 2007, 'Tritium distribution measurement of JET Mk II SRP divertor tiles', Journal of Nuclear Materials, vol. 363-365, pp. 960-965. https://doi.org/10.1016/j.jnucmat.2007.01.191

    Tritium distribution measurement of JET Mk II SRP divertor tiles. / Tanabe, T.; Sugiyama, K.; Renvall, T.; Likonen, Jari; Penttinen, L.; Vainonen-Ahlgren, Elizaveta; Coad, J.P.

    In: Journal of Nuclear Materials, Vol. 363-365, 2007, p. 960-965.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Tritium distribution measurement of JET Mk II SRP divertor tiles

    AU - Tanabe, T.

    AU - Sugiyama, K.

    AU - Renvall, T.

    AU - Likonen, Jari

    AU - Penttinen, L.

    AU - Vainonen-Ahlgren, Elizaveta

    AU - Coad, J.P.

    PY - 2007

    Y1 - 2007

    N2 - 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.

    AB - 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.

    KW - tritium

    KW - JET

    KW - divertor

    KW - carbon-based materials

    KW - hydrogen retention

    KW - ITER

    KW - fusion energy

    KW - plasma

    KW - tungsten

    U2 - 10.1016/j.jnucmat.2007.01.191

    DO - 10.1016/j.jnucmat.2007.01.191

    M3 - Article

    VL - 363-365

    SP - 960

    EP - 965

    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    ER -