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

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

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    53 Citations (Scopus)


    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
    Publication statusPublished - 2015
    MoE publication typeA1 Journal article-refereed


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