Divertor heat load in ASDEX Upgrade L-mode in presence of external magnetic perturbation

被引:34
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
thermography; scrape-off layer; magnetic perturbation; heat exhaust; divertor; tokamak; SCRAPE-OFF LAYER; TRANSPORT; DESIGN;
D O I
10.1088/1361-6587/aa75e7
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Power exhaust is one of the major challenges for a future fusion device. Applying a nonaxisymmetric external magnetic perturbation is one technique that is studied in order to mitigate or suppress large edge localized modes which accompany the high confinement regime in tokamaks. The external magnetic perturbation induces breaking in the axisymmetry of a tokamak and leads to a 2D heat flux pattern on the divertor target. The 2D heat flux pattern at the outer divertor target is studied on ASDEX Upgrade in stationary L- mode discharges. The amplitude of the 2D characteristic of the heat flux depends on the alignment between the field lines at the edge and the vacuum response of the applied magnetic perturbation spectrum. The 2D characteristic reduces with increasing density. The increasing divertor broadening, S, with increasing density is proposed as the main actuator. This is supported by a generic model using field line tracing and the vacuum field approach that is in quantitative agreement with the measured heat flux. The perturbed heat flux, averaged over a full toroidal rotation of the magnetic perturbation, is identical to the non- perturbed heat flux without magnetic perturbation. The transport qualifiers, power fall- off length lambda(q) and divertor broadening, S, are the same within the uncertainty compared to the unperturbed reference. No additional cross field transport is observed.
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页数:16
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共 40 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] Method for comparison of tokamak divertor strike point data with magnetic perturbation models
    Cahyna, P.
    Peterka, M.
    Nardon, E.
    Frerichs, H.
    Panek, R.
    [J]. NUCLEAR FUSION, 2014, 54 (06)
  • [3] UPDATE ON DESIGN OF THE ITER IN-VESSEL COILS
    Daly, E. F.
    Ioki, K.
    Loarte, A.
    Martin, A.
    Brooks, A.
    Heitzenroeder, P.
    Kalish, M.
    Neumeyer, C.
    Titus, P.
    Zhai, Y.
    Wu, Y.
    Jin, H.
    Long, F.
    Song, Y.
    Wang, Z.
    Pillsbury, R.
    Feng, J.
    Bohm, T.
    Sawan, M.
    Preble, J.
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2013, 64 (02) : 168 - 175
  • [4] Two dimensional modelling approach to transport properties of the TEXTOR-DED laminar zone
    Eich, T
    Reiser, D
    Finken, KH
    [J]. NUCLEAR FUSION, 2000, 40 (10) : 1757 - 1772
  • [5] 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)
  • [6] Suppression of large edge-localized modes in high-confinement DIII-D plasmas with a stochastic magnetic boundary
    Evans, TE
    Moyer, RA
    Thomas, PR
    Watkins, JG
    Osborne, TH
    Boedo, JA
    Doyle, EJ
    Fenstermacher, ME
    Finken, KH
    Groebner, RJ
    Groth, M
    Harris, JH
    La Haye, RJ
    Lasnier, CJ
    Masuzaki, S
    Ohyabu, N
    Pretty, DG
    Rhodes, TL
    Reimerdes, H
    Rudakov, DL
    Schaffer, MJ
    Wang, G
    Zeng, L
    [J]. PHYSICAL REVIEW LETTERS, 2004, 92 (23) : 235003 - 1
  • [7] 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)
  • [8] Faitsch M., 2017, NUCL MAT ENERGY
  • [9] First modelling of the textor DED near field divertor
    Finken, KH
    Eich, T
    Kaleck, A
    [J]. NUCLEAR FUSION, 1998, 38 (04) : 515 - 529
  • [10] GOURDON C, 1971, NUCL FUSION, V11, P161, DOI 10.1088/0029-5515/11/2/010