中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths

文献类型:期刊论文

作者Chen, B.1,2; Xu, X. Q.2; Xia, T. Y.2,3; Li, N. M.4; Porkolab, M.5; Edlund, E.5; LaBombard, B.5; Terry, J.5; Hughes, J. W.5; Ye, M. Y.1
刊名PHYSICS OF PLASMAS
出版日期2018-05-01
卷号25期号:5页码:13
ISSN号1070-664X
DOI10.1063/1.5016582
通讯作者Xu, X. Q.(xxu@llnl.gov)
英文摘要The heat flux distributions on divertor targets in H-mode plasmas are serious concerns for future devices. We seek to simulate the tokamak boundary plasma turbulence and heat transport in the edge localized mode-suppressed regimes. The improved BOUT++ model shows that not only I-p but also the radial electric field E-r plays an important role on the turbulence behavior and sets the heat flux width. Instead of calculating E-r from the pressure gradient term (diamagnetic E-r), it is calculated from the plasma transport equations with the sheath potential in the scrape-off layer and the plasma density and temperature profiles inside the separatrix from the experiment. The simulation results with the new E-r model have better agreement with the experiment than using the diamagnetic E-r model: (1) The electromagnetic turbulence in enhanced D-alpha H-mode shows the characteristics of quasi-coherent modes (QCMs) and broadband turbulence. The mode spectra are in agreement with the phase contrast imaging data and almost has no change in comparison to the cases which use the diamagnetic E-r model; (2) the self-consistent boundary E-r is needed for the turbulence simulations to get the consistent heat flux width with the experiment; (3) the frequencies of the QCMs are proportional to E-r, while the divertor heat flux widths are inversely proportional to E-r; and (4) the BOUT++ turbulence simulations yield a similar heat flux width to the experimental Eich scaling law and the prediction from the Goldston heuristic drift model. Published by AIP Publishing.
WOS关键词ALCATOR C-MOD ; EDGE-LOCALIZED MODES ; NEUTRAL-BEAM ; H-MODE ; CONFINEMENT ; DISCHARGES ; TRANSPORT ; SIMULATIONS ; ASDEX ; POWER
资助项目CSC[201506340019] ; U.S. Department of Energy by Lawrence Livermore National Laboratory[DE-AC52-7NA27344] ; U.S. Department of Energy by Lawrence Livermore National Laboratory[LLNL-JRNL-742019] ; U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences ; U.S. Department of Energy[DE-FC02-99ER54512] ; U.S. Department of Energy[DE-SC0014264] ; National Natural Science Foundation of China[11375191]
WOS研究方向Physics
语种英语
WOS记录号WOS:000433961800121
出版者AMER INST PHYSICS
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源URL[http://ir.hfcas.ac.cn:8080/handle/334002/38150]  
专题合肥物质科学研究院_中科院等离子体物理研究所
通讯作者Xu, X. Q.
作者单位1.Univ Sci & Technol China, Sch Phys Sci, Hefei 230026, Anhui, Peoples R China
2.Lawrence Livermore Natl Lab, Livermore, CA 94550 USA
3.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
4.Dalian Univ Technol, Dalian 116024, Peoples R China
5.MIT, Plasma Sci & Fus Ctr, 77 Massachusetts Ave, Cambridge, MA 02139 USA
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Chen, B.,Xu, X. Q.,Xia, T. Y.,et al. Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths[J]. PHYSICS OF PLASMAS,2018,25(5):13.
APA Chen, B..,Xu, X. Q..,Xia, T. Y..,Li, N. M..,Porkolab, M..,...&Wan, Y. X..(2018).Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths.PHYSICS OF PLASMAS,25(5),13.
MLA Chen, B.,et al."Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths".PHYSICS OF PLASMAS 25.5(2018):13.

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来源:合肥物质科学研究院

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