SOLPS-ITER Modeling of the Alcator C-Mod Divertor Plasma

被引:21
作者
Dekeyser, Wouter [1 ]
Bonnin, Xavier [1 ]
Lisgo, Steven W. [1 ]
Pitts, Richard A. [1 ]
Brunner, Dan [2 ]
Labombard, Brian [2 ]
Terry, Jim L. [2 ]
机构
[1] ITER Org, Route Vinon Sur Verdon,CS 90046, F-130670 St Paul Les Durance, France
[2] MIT, Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA
关键词
edge plasma modeling; divertor modeling; scrape-off layer; SOLPS-ITER; Alcator C-Mod;
D O I
10.1585/pfr.11.1403103
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
SOLPS-ITER is a new edge code package that will be developed and maintained at the ITER Organization [X. Bonnin et al., Plasma Fusion Res. 11, 1403102 (2016)], in close collaboration with the wider SOLPS community, and will be used to support the design of the ITER divertor [A. S. Kukushkin et al., Fusion Eng. Des. 86, 2865 (2011)]. In this paper, we report on the first application of the code to the modeling of the Alcator C-Mod divertor. With its high density, high magnetic field, and strong ITER-like target shaping, C-Mod is of particular interest to ITER in terms of plasma and neutral parameters in the divertor. We show that with a fluid neutral model, we can qualitatively reproduce the observed particle fluxes to inner and outer targets under partially detached conditions. However, simulated electron temperatures in the divertor are much too low. A number of physics and numerical reasons are proposed to resolve this issue and serve as a guideline for further development of the code. (C) 2016 The Japan Society of Plasma Science and Nuclear Fusion Research
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页数:6
相关论文
共 23 条
[1]   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 [J].
Aho-Mantila, L. ;
Wischmeier, M. ;
Mueller, H. W. ;
Potzel, S. ;
Coster, D. P. ;
Bonnin, X. ;
Conway, G. D. .
NUCLEAR FUSION, 2012, 52 (10)
[2]   Tokamak plasma edge modelling including the main chamber wall [J].
Baelmans, M. ;
Boerner, P. ;
Dekeyser, W. ;
Reiter, D. .
NUCLEAR FUSION, 2011, 51 (08)
[3]   Modelling and consequences of drift effects in the edge plasma of Alcator C-Mod [J].
Bonnin, X ;
Coster, D ;
Schneider, R ;
Reiter, D ;
Rozhansky, V ;
Voskoboynikov, S .
JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :301-304
[4]   Improved modelling of detachment and neutral-dominated regimes using the SOLPS B2-Eirene code [J].
Bonnin, X ;
Coster, D ;
Pitcher, CS ;
Schneider, R ;
Reiter, D ;
Rozhansky, V ;
Voskoboynikov, S ;
Bürbaumer, H .
JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :909-913
[5]   Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling [J].
Bonnin, Xavier ;
Dekeyser, Wouter ;
Pitts, Richard ;
Coster, David ;
Voskoboynikov, Serguey ;
Wiesen, Sven .
PLASMA AND FUSION RESEARCH, 2016, 11 :1-6
[6]   Divertor 'death-ray' explained: An artifact of a Langmuir probe operating at negative bias in a high-recycling divertor [J].
Brunner, D. ;
Umansky, M. V. ;
LaBombard, B. ;
Rognlien, T. D. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 438 :S1196-S1199
[7]   An assessment of ion temperature measurements in the boundary of the Alcator C-Mod tokamak and implications for ion fluid heat flux limiters [J].
Brunner, D. ;
LaBombard, B. ;
Churchill, R. M. ;
Hughes, J. ;
Lipschultz, B. ;
Ochoukov, R. ;
Rognlien, T. D. ;
Theiler, C. ;
Walk, J. ;
Umansky, M. V. ;
Whyte, D. .
PLASMA PHYSICS AND CONTROLLED FUSION, 2013, 55 (09)
[8]  
Dekeyser Wouter, 2014, Proceedings in Applied Mathematics and Mechanics, V14, P1017, DOI 10.1002/pamm.201410487
[9]   Filamentary transport in the private flux region in MAST [J].
Harrison, J. R. ;
Fishpool, G. M. ;
Dudson, B. D. .
JOURNAL OF NUCLEAR MATERIALS, 2015, 463 :757-760
[10]   Finalizing the ITER divertor design: The key role of SOLPS modeling [J].
Kukushkin, A. S. ;
Pacher, H. D. ;
Kotov, V. ;
Pacher, G. W. ;
Reiter, D. .
FUSION ENGINEERING AND DESIGN, 2011, 86 (12) :2865-2873