Outer divertor of ASDEX Upgrade in low-density L-mode discharges in forward and reversed magnetic field: I. Comparison between measured plasma conditions and SOLPS5.0 code calculations

被引:43
作者
Aho-Mantila, L. [1 ]
Wischmeier, M. [2 ]
Mueller, H. W. [2 ]
Potzel, S. [2 ]
Coster, D. P. [2 ]
Bonnin, X. [3 ]
Conway, G. D. [2 ]
机构
[1] VTT Tech Res Ctr Finland, FI-02044 Espoo, Finland
[2] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[3] Univ Paris 13, CNRS, LSPM, F-93430 Villetaneuse, France
基金
芬兰科学院;
关键词
SCRAPE-OFF-LAYER; EDGE PLASMA; TRANSPORT; FLOW; PROBES;
D O I
10.1088/0029-5515/52/10/103006
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
The scrape-off layer and divertor plasma conditions have been carefully analysed in dedicated ASDEX Upgrade experiments consisting of low-density L-mode discharges, with both forward and reversed toroidal magnetic fields and plasma currents. In the forward field, the outer divertor plasma is in a low-recycling regime with peak target temperature above 25 eV. In the reversed field with similar main plasma parameters, the target temperature is below 15 eV and the density is 5 times as high as in the forward field, indicating a higher recycling regime in the outer divertor. The SOLPS5.0 code package is used to model these divertor plasmas. Specifically, it is tested whether a combination of input assumptions exists that enables matching the code solution to all outer divertor diagnostic measurements, and whether these assumptions are compatible with constraints imposed by measurements outside the outer divertor. In the forward field, a good level of agreement with multiple outer target measurements is found with assumptions that simultaneously match the measured density and temperature profiles at the outer midplane, where the uncertainty in the radial position of the separatrix is +/- 0.5 cm. Similar approaches made previously for higher recycling regimes have not led to such a good consistency between all modelled and measured outer divertor parameters. In the reversed field with higher recycling in the outer divertor, a solution consistent with the outer target Langmuir probe measurements cannot be obtained, at least not without significantly compromising the match to the upstream profile measurements. Significant mismatches are observed also between the modelled and measured upstream Mach number in the forward field. These discrepancies question the global validity of the plasma solutions, and their origin is not yet clear. In part II (Aho-Mantila L. et al 2012 Nucl. Fusion 52 103007), the analysis of outer divertor conditions is complemented by local impurity migration studies, using the divertor plasma solutions presented in this paper.
引用
收藏
页数:12
相关论文
共 36 条
  • [1] Outer divertor of ASDEX Upgrade in low-density L-mode discharges in forward and reversed magnetic field: II. Analysis of local impurity migration
    Aho-Mantila, L.
    Wischmeier, M.
    Krieger, K.
    Rohde, V.
    Hakola, A.
    Potzel, S.
    Kirschner, A.
    Borodin, D.
    [J]. NUCLEAR FUSION, 2012, 52 (10)
  • [2] Effect of E x B driven transport on the deposition of carbon in the outer divertor of ASDEX Upgrade
    Aho-Mantila, L.
    Wischmeier, M.
    Krieger, K.
    Rohde, V.
    Mueller, H. W.
    Coster, D. P.
    Groth, M.
    Kirschner, A.
    Neu, R.
    Potzel, S.
    Sieglin, B.
    Wolfrum, E.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 415 (01) : S231 - S234
  • [3] Modelling of Carbon Transport in the Outer Divertor Plasma of ASDEX Upgrade
    Aho-Mantila, L.
    Wischmeier, M.
    Airila, M. I.
    Chankin, A. V.
    Coster, D. P.
    Fuchs, Ch
    Groth, M.
    Kirschner, A.
    Krieger, K.
    Mueller, H. W.
    Wolfrum, E.
    [J]. CONTRIBUTIONS TO PLASMA PHYSICS, 2010, 50 (3-5) : 439 - 444
  • [4] Asakura N., 2009, PLASMA FUSION RES, V4
  • [5] Modelling and consequences of drift effects in the edge plasma of Alcator C-Mod
    Bonnin, X
    Coster, D
    Schneider, R
    Reiter, D
    Rozhansky, V
    Voskoboynikov, S
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) : 301 - 304
  • [6] Bonnin X, 2005, P 32 EPS C PLASM PHY, V29C
  • [7] Carthy P.J.M., 2012, PLASMA PHYS CONTROL, V54
  • [8] A possible role of radial electric field in driving parallel ion flow in scrape-off layer of divertor tokamaks
    Chankin, A. V.
    Coster, D. P.
    Asakura, N.
    Corrigan, G.
    Erents, S. K.
    Fundamenski, W.
    Mueller, H. W.
    Pitts, R. A.
    Stangeby, P. C.
    Wischmeier, M.
    [J]. NUCLEAR FUSION, 2007, 47 (08) : 762 - 772
  • [9] SOLPS modelling of ASDEX upgrade H-mode plasma
    Chankin, A. V.
    Coster, D. P.
    Dux, R.
    Fuchs, Ch
    Haas, G.
    Herrmann, A.
    D Horton, L.
    Kallenbach, A.
    Kaufmann, M.
    Konz, Ch
    Lackner, K.
    Maggi, C.
    Mueller, H. W.
    Neuhauser, J.
    Pugno, R.
    Reich, M.
    Schneider, W.
    [J]. PLASMA PHYSICS AND CONTROLLED FUSION, 2006, 48 (06) : 839 - 868
  • [10] Conway G. D., 2010, Plasma Fusion Res, V5, pS2000, DOI [10.1585/pfr.5.S2005, DOI 10.1585/PFR.5.S2005]