2D heat flux in ASDEX Upgrade L-Mode with magnetic perturbation

被引:12
作者
Faitsch, M. [1 ]
Sieglin, B. [1 ]
Eich, T. [1 ]
Herrmann, A. [1 ]
Suttrop, W. [1 ]
机构
[1] Max Planck Inst Plasma Phys, Boltzmannstr 2, D-85748 Garching, Germany
关键词
Heat exhaust; Magnetic perturbation; Scrape-offlayer; Infrared thermography; ENERGY;
D O I
10.1016/j.nme.2017.03.008
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Power exhaust is one of the major challenges for a future fusion device like ITER. Future devices are foreseen to operate in a regime that exhibits periodic outbursts of particles and energy, so called edge localised modes (ELMs). These ELMs might limit the life time of the divertor target. One of the techniques that is studied in order to control ELMs is the application of a non-axisymmetric magnetic perturbation (MP). This technique leads to a 2D heat flux pattern at the divertor target. The 2D heat flux pattern is characterised for a perturbation with a toroidal mode number n = 2. The lobe structure is visible with a resonant configuration in a low density L-Mode. Varying the differential phase reduces the extent of the heat flux modulation compared to the axisymmetric reference. The heat flux distribution shows no significant modulation with the differential phase opposite to the resonant configuration. The toroidally averaged profile is described by an 1D diffusive model for all differential phases. No significant deviation between the axisymmetric reference and the averaged profiles is observed for both transport qualifiers, power fall-offlength lambda(q) and divertor broadening S. It was reported from previous studies in ASDEX Upgrade, that in L-Mode both lambda(q) and S increase with increasing density. This dependence is confirmed for the axisymmetric reference phase. The toroidally averaged heat flux profiles with MP show the same increase with density as the reference without MP. The modulation of the heat flux decreases with increasing density. This is attributed to the increasing divertor broadening S which distributes the heat flux more uniformly. (C) 2017TheAuthors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license. (http://creativecommons.org/licenses/by-nc-nd/4.0/)
引用
收藏
页码:1020 / 1024
页数:5
相关论文
共 22 条
  • [1] Modification of divertor heat and particle flux profiles with applied 3D fields in NSTX H-mode plasmas
    Ahn, J. -W.
    Canik, J. M.
    Soukhanovskii, V. A.
    Maingi, R.
    Battaglia, D. J.
    [J]. NUCLEAR FUSION, 2010, 50 (04)
  • [2] An experimental investigation of the high density transition of the scrape-off layer transport in ASDEX Upgrade
    Carralero, D.
    Birkenmeier, G.
    Mueller, H. W.
    Manz, P.
    deMarne, P.
    Mueller, S. H.
    Reimold, F.
    Stroth, U.
    Wischmeier, M.
    Wolfrum, E.
    [J]. NUCLEAR FUSION, 2014, 54 (12)
  • [3] Inter-ELM Power Decay Length for JET and ASDEX Upgrade: Measurement and Comparison with Heuristic Drift-Based Model
    Eich, T.
    Sieglin, B.
    Scarabosio, A.
    Fundamenski, W.
    Goldston, R. J.
    Herrmann, A.
    [J]. PHYSICAL REVIEW LETTERS, 2011, 107 (21)
  • [4] Change of the scrape-off layer power width with the toroidal B-field direction in ASDEX upgrade
    Faitsch, M.
    Sieglin, B.
    Eich, T.
    Sun, H. J.
    Herrmann, A.
    [J]. PLASMA PHYSICS AND CONTROLLED FUSION, 2015, 57 (07)
  • [5] Strike point splitting in the heat and particle flux profiles compared with the edge magnetic topology in a n=2 resonant magnetic perturbation field at JET
    Harting, D. M.
    Liang, Y.
    Jachmich, S.
    Koslowski, R.
    Arnoux, G.
    Devaux, S.
    Eich, T.
    Nardon, E.
    Reiter, D.
    Thomsen, H.
    [J]. NUCLEAR FUSION, 2012, 52 (05)
  • [6] ENERGY FLUX TO THE ASDEX-UPGRADE DIVERTOR PLATES DETERMINED BY THERMOGRAPHY AND CALORIMETRY
    HERRMANN, A
    JUNKER, W
    GUNTHER, K
    BOSCH, S
    KAUFMANN, M
    NEUHAUSER, J
    PAUTASSO, G
    RICHTER, T
    SCHNEIDER, R
    [J]. PLASMA PHYSICS AND CONTROLLED FUSION, 1995, 37 (01) : 17 - 29
  • [7] Overview of the results on divertor heat loads in RMP controlled H-mode plasmas on DIII-D
    Jakubowski, M. W.
    Evans, T. E.
    Fenstermacher, M. E.
    Groth, M.
    Lasnier, C. J.
    Leonard, A. W.
    Schmitz, O.
    Watkins, J. G.
    Eich, T.
    Fundamenski, W.
    Moyer, R. A.
    Wolf, R. C.
    Baylor, L. B.
    Boedo, J. A.
    Burrell, K. H.
    Frerichs, H.
    deGrassie, J. S.
    Gohil, P.
    Joseph, I.
    Mordijck, S.
    Lehnen, M.
    Petty, C. C.
    Pinsker, R. I.
    Reiter, D.
    Rhodes, T. L.
    Samm, U.
    Schaffer, M. J.
    Snyder, P. B.
    Stoschus, H.
    Osborne, T.
    Unterberg, B.
    Unterberg, E.
    West, W. P.
    [J]. NUCLEAR FUSION, 2009, 49 (09)
  • [8] ELM control strategies and tools: status and potential for ITER
    Lang, P. T.
    Loarte, A.
    Saibene, G.
    Baylor, L. R.
    Becoulet, M.
    Cavinato, M.
    Clement-Lorenzo, S.
    Daly, E.
    Evans, T. E.
    Fenstermacher, M. E.
    Gribov, Y.
    Horton, L. D.
    Lowry, C.
    Martin, Y.
    Neubauer, O.
    Oyama, N.
    Schaffer, M. J.
    Stork, D.
    Suttrop, W.
    Thomas, P.
    Tran, M.
    Wilson, H. R.
    Kavin, A.
    Schmitz, O.
    [J]. NUCLEAR FUSION, 2013, 53 (04)
  • [9] Progress on the application of ELM control schemes to ITER scenarios from the non-active phase to DT operation
    Loarte, A.
    Huijsmans, G.
    Futatani, S.
    Baylor, L. R.
    Evans, T. E.
    Orlov, D. M.
    Schmitz, O.
    Becoulet, M.
    Cahyna, P.
    Gribov, Y.
    Kavin, A.
    Naik, A. Sashala
    Campbell, D. J.
    Casper, T.
    Daly, E.
    Frerichs, H.
    Kischner, A.
    Laengner, R.
    Lisgo, S.
    Pitts, R. A.
    Saibene, G.
    Wingen, A.
    [J]. NUCLEAR FUSION, 2014, 54 (03)
  • [10] Characteristics of type I ELM energy and particle losses in existing devices and their extrapolation to ITER
    Loarte, A
    Saibene, G
    Sartori, R
    Campbell, D
    Becoulet, M
    Horton, L
    Eich, T
    Herrmann, A
    Matthews, G
    Asakura, N
    Chankin, A
    Leonard, A
    Porter, G
    Federici, G
    Janeschitz, G
    Shimada, M
    Sugihara, M
    [J]. PLASMA PHYSICS AND CONTROLLED FUSION, 2003, 45 (09) : 1549 - 1569