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

    43 Citations (Scopus)


    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
    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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