Fuel retention in JET ITER-Like Wall from post-mortem analysis

K. Heinola (Corresponding Author), A. Widdowson, J. Likonen, E. Alves, A. Baron-Wiechec, N. Barradas, S. Brzinsek, N. Catarino, P. Coad, S. Koivuranta, G.F. Matthews, M. Mayer, P Petersson, JET-EFDA Contributors

    Research output: Contribution to journalArticleScientificpeer-review

    33 Citations (Scopus)

    Abstract

    Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.
    Original languageEnglish
    Pages (from-to)961-965
    JournalJournal of Nuclear Materials
    Volume463
    DOIs
    Publication statusPublished - 2015
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Tile
    tiles
    Deuterium
    Limiters
    Ion beams
    Erosion
    Gases
    closures
    erosion
    Impurities
    deuterium
    Plasmas
    chambers
    ion beams
    impurities
    gases
    Experiments

    Cite this

    Heinola, K., Widdowson, A., Likonen, J., Alves, E., Baron-Wiechec, A., Barradas, N., ... Contributors, JET-EFDA. (2015). Fuel retention in JET ITER-Like Wall from post-mortem analysis. Journal of Nuclear Materials, 463, 961-965. https://doi.org/10.1016/j.jnucmat.2014.12.098
    Heinola, K. ; Widdowson, A. ; Likonen, J. ; Alves, E. ; Baron-Wiechec, A. ; Barradas, N. ; Brzinsek, S. ; Catarino, N. ; Coad, P. ; Koivuranta, S. ; Matthews, G.F. ; Mayer, M. ; Petersson, P ; Contributors, JET-EFDA. / Fuel retention in JET ITER-Like Wall from post-mortem analysis. In: Journal of Nuclear Materials. 2015 ; Vol. 463. pp. 961-965.
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    title = "Fuel retention in JET ITER-Like Wall from post-mortem analysis",
    abstract = "Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.",
    author = "K. Heinola and A. Widdowson and J. Likonen and E. Alves and A. Baron-Wiechec and N. Barradas and S. Brzinsek and N. Catarino and P. Coad and S. Koivuranta and G.F. Matthews and M. Mayer and P Petersson and JET-EFDA Contributors",
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    Heinola, K, Widdowson, A, Likonen, J, Alves, E, Baron-Wiechec, A, Barradas, N, Brzinsek, S, Catarino, N, Coad, P, Koivuranta, S, Matthews, GF, Mayer, M, Petersson, P & Contributors, JET-EFDA 2015, 'Fuel retention in JET ITER-Like Wall from post-mortem analysis', Journal of Nuclear Materials, vol. 463, pp. 961-965. https://doi.org/10.1016/j.jnucmat.2014.12.098

    Fuel retention in JET ITER-Like Wall from post-mortem analysis. / Heinola, K. (Corresponding Author); Widdowson, A.; Likonen, J.; Alves, E.; Baron-Wiechec, A.; Barradas, N.; Brzinsek, S.; Catarino, N.; Coad, P.; Koivuranta, S.; Matthews, G.F.; Mayer, M.; Petersson, P; Contributors, JET-EFDA.

    In: Journal of Nuclear Materials, Vol. 463, 2015, p. 961-965.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Fuel retention in JET ITER-Like Wall from post-mortem analysis

    AU - Heinola, K.

    AU - Widdowson, A.

    AU - Likonen, J.

    AU - Alves, E.

    AU - Baron-Wiechec, A.

    AU - Barradas, N.

    AU - Brzinsek, S.

    AU - Catarino, N.

    AU - Coad, P.

    AU - Koivuranta, S.

    AU - Matthews, G.F.

    AU - Mayer, M.

    AU - Petersson, P

    AU - Contributors, JET-EFDA

    N1 - Project code: 104445

    PY - 2015

    Y1 - 2015

    N2 - Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.

    AB - Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.

    U2 - 10.1016/j.jnucmat.2014.12.098

    DO - 10.1016/j.jnucmat.2014.12.098

    M3 - Article

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    JF - Journal of Nuclear Materials

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