Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

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

    Research output: Contribution to journalArticleScientificpeer-review

    12 Citations (Scopus)

    Abstract

    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
    Volume415
    Issue number1
    DOIs
    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

    Fingerprint

    Carbon
    scaling
    Erosion
    carbon
    estimates
    Fluxes
    erosion
    Tritium
    Limiters
    tritium
    predictions
    vessels
    configurations

    Cite this

    Tsitrone, E. ; Pégourié, B. ; Marandet, Y. ; Likonen, Jari. / Multi machine scaling of fuel retention in 4 carbon dominated tokamaks. In: Journal of Nuclear Materials. 2011 ; Vol. 415, No. 1. pp. S735-S739.
    @article{6ade3140bc224033b068804550b03111,
    title = "Multi machine scaling of fuel retention in 4 carbon dominated tokamaks",
    abstract = "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.",
    author = "E. Tsitrone and B. P{\'e}gouri{\'e} and Y. Marandet and Jari Likonen",
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    Multi machine scaling of fuel retention in 4 carbon dominated tokamaks. / Tsitrone, E. (Corresponding Author); Pégourié, B.; Marandet, Y.; Likonen, Jari.

    In: Journal of Nuclear Materials, Vol. 415, No. 1, 2011, p. S735-S739.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

    AU - Tsitrone, E.

    AU - Pégourié, B.

    AU - Marandet, Y.

    AU - Likonen, Jari

    PY - 2011

    Y1 - 2011

    N2 - 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.

    AB - 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.

    U2 - 10.1016/j.jnucmat.2011.01.132

    DO - 10.1016/j.jnucmat.2011.01.132

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    SP - S735-S739

    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    IS - 1

    ER -