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

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36 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

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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.
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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.",
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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

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AU - Wischmeier, M.

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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

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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.

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