Assessment of edge modeling in support of ITER

M. Wischmeier (Corresponding Author), M. Groth, S. Wiesen, S. Potzel, Leena Aho-Mantila, D.P. Coster, R. Dux, C. Fuchs, A. Kallenbach, H.W. Müller, D. Reider, A. Scarabosio, ASDEX Upgrade Team

    Research output: Contribution to journalArticleScientificpeer-review

    38 Citations (Scopus)

    Abstract

    Multi-fluid plasma edge code packages, usually coupled to Monte-Carlo transport codes for neutrals are in wide use in the fusion community to simulate the SOL and divertor. A status of the current code validation effort is presented using experimental data of Ohmic and L-mode discharges from ASDEX Upgrade for He in forward toroidal field, BT, only and for D fueled in forward and reversed BT in lower single null configurations. While satisfactory agreement between simulated and experimental data can be obtained for both divertors as long as one of the two divertors is not strongly recombining, the qualitative behavior as a function of line averaged density cannot be recovered in the simulations for higher recycling regimes. This holds independently of field direction or fueling species. Semi-empirical models and thus far not included physics models are discussed.
    Original languageEnglish
    Pages (from-to)S523-S529
    Number of pages7
    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

    Fueling
    Recycling
    Fusion reactions
    refueling
    Physics
    recycling
    Plasmas
    Fluids
    fusion
    physics
    fluids
    configurations
    simulation
    Direction compound

    Cite this

    Wischmeier, M., Groth, M., Wiesen, S., Potzel, S., Aho-Mantila, L., Coster, D. P., ... Team, ASDEX. U. (2011). Assessment of edge modeling in support of ITER. Journal of Nuclear Materials, 415(1), S523-S529. https://doi.org/10.1016/j.jnucmat.2011.02.020
    Wischmeier, M. ; Groth, M. ; Wiesen, S. ; Potzel, S. ; Aho-Mantila, Leena ; Coster, D.P. ; Dux, R. ; Fuchs, C. ; Kallenbach, A. ; Müller, H.W. ; Reider, D. ; Scarabosio, A. ; Team, ASDEX Upgrade. / Assessment of edge modeling in support of ITER. In: Journal of Nuclear Materials. 2011 ; Vol. 415, No. 1. pp. S523-S529.
    @article{6bdcc58e5fac41219a34889bd45dc5d5,
    title = "Assessment of edge modeling in support of ITER",
    abstract = "Multi-fluid plasma edge code packages, usually coupled to Monte-Carlo transport codes for neutrals are in wide use in the fusion community to simulate the SOL and divertor. A status of the current code validation effort is presented using experimental data of Ohmic and L-mode discharges from ASDEX Upgrade for He in forward toroidal field, BT, only and for D fueled in forward and reversed BT in lower single null configurations. While satisfactory agreement between simulated and experimental data can be obtained for both divertors as long as one of the two divertors is not strongly recombining, the qualitative behavior as a function of line averaged density cannot be recovered in the simulations for higher recycling regimes. This holds independently of field direction or fueling species. Semi-empirical models and thus far not included physics models are discussed.",
    author = "M. Wischmeier and M. Groth and S. Wiesen and S. Potzel and Leena Aho-Mantila and D.P. Coster and R. Dux and C. Fuchs and A. Kallenbach and H.W. M{\"u}ller and D. Reider and A. Scarabosio and Team, {ASDEX Upgrade}",
    year = "2011",
    doi = "10.1016/j.jnucmat.2011.02.020",
    language = "English",
    volume = "415",
    pages = "S523--S529",
    journal = "Journal of Nuclear Materials",
    issn = "0022-3115",
    publisher = "Elsevier",
    number = "1",

    }

    Wischmeier, M, Groth, M, Wiesen, S, Potzel, S, Aho-Mantila, L, Coster, DP, Dux, R, Fuchs, C, Kallenbach, A, Müller, HW, Reider, D, Scarabosio, A & Team, ASDEXU 2011, 'Assessment of edge modeling in support of ITER', Journal of Nuclear Materials, vol. 415, no. 1, pp. S523-S529. https://doi.org/10.1016/j.jnucmat.2011.02.020

    Assessment of edge modeling in support of ITER. / Wischmeier, M. (Corresponding Author); Groth, M.; Wiesen, S.; Potzel, S.; Aho-Mantila, Leena; Coster, D.P.; Dux, R.; Fuchs, C.; Kallenbach, A.; Müller, H.W.; Reider, D.; Scarabosio, A.; Team, ASDEX Upgrade.

    In: Journal of Nuclear Materials, Vol. 415, No. 1, 2011, p. S523-S529.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Assessment of edge modeling in support of ITER

    AU - Wischmeier, M.

    AU - Groth, M.

    AU - Wiesen, S.

    AU - Potzel, S.

    AU - Aho-Mantila, Leena

    AU - Coster, D.P.

    AU - Dux, R.

    AU - Fuchs, C.

    AU - Kallenbach, A.

    AU - Müller, H.W.

    AU - Reider, D.

    AU - Scarabosio, A.

    AU - Team, ASDEX Upgrade

    PY - 2011

    Y1 - 2011

    N2 - Multi-fluid plasma edge code packages, usually coupled to Monte-Carlo transport codes for neutrals are in wide use in the fusion community to simulate the SOL and divertor. A status of the current code validation effort is presented using experimental data of Ohmic and L-mode discharges from ASDEX Upgrade for He in forward toroidal field, BT, only and for D fueled in forward and reversed BT in lower single null configurations. While satisfactory agreement between simulated and experimental data can be obtained for both divertors as long as one of the two divertors is not strongly recombining, the qualitative behavior as a function of line averaged density cannot be recovered in the simulations for higher recycling regimes. This holds independently of field direction or fueling species. Semi-empirical models and thus far not included physics models are discussed.

    AB - Multi-fluid plasma edge code packages, usually coupled to Monte-Carlo transport codes for neutrals are in wide use in the fusion community to simulate the SOL and divertor. A status of the current code validation effort is presented using experimental data of Ohmic and L-mode discharges from ASDEX Upgrade for He in forward toroidal field, BT, only and for D fueled in forward and reversed BT in lower single null configurations. While satisfactory agreement between simulated and experimental data can be obtained for both divertors as long as one of the two divertors is not strongly recombining, the qualitative behavior as a function of line averaged density cannot be recovered in the simulations for higher recycling regimes. This holds independently of field direction or fueling species. Semi-empirical models and thus far not included physics models are discussed.

    U2 - 10.1016/j.jnucmat.2011.02.020

    DO - 10.1016/j.jnucmat.2011.02.020

    M3 - Article

    VL - 415

    SP - S523-S529

    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    IS - 1

    ER -