Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

E. Tsitrone (Corresponding Author), B. Pégourié, Y. Marandet, Jari Likonen

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    In order to benchmark predictions for the in vessel tritium inventory in ITER, a survey of fuel retention measured in 4 carbon dominated tokamaks (TEXTOR, ASDEX Upgrade in the 2002–2003 carbon configuration, Tore Supra and JET) was performed, showing retention rates from ∼1 g D/h in TEXTOR (L mode, limiter machine) up to ∼6–12 g D/h in AUG (H mode, divertor machine). A simple scaling used for ITER predictions is applied for comparison with experimental values: (1) estimate of wall fluxes, (2) estimate of the gross carbon erosion, (3) estimate of the net erosion/redeposition assuming a redeposition fraction and (4) estimate of the retention rate using D/C ratio scalings. The validity of each step is discussed, showing that this approach yields the right order of magnitude, but tends to underestimate the experimental values unless a high wall flux, a low local redeposition fraction and/or a high D/C ratio are used.
    Original languageEnglish
    Pages (from-to)S735-S739
    Number of pages5
    JournalJournal of Nuclear Materials
    Issue number1
    Publication statusPublished - 2011
    MoE publication typeA1 Journal article-refereed
    Event19th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, PSI-19 - San Diego, United States
    Duration: 24 May 201028 May 2010


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