Simulation of divertor heat flux width on EAST by BOUT plus plus transport code

doi:10.1088/1741-4326/ab70d6

	Simulation of divertor heat flux width on EAST by BOUT plus plus transport code
	Deng, G. Z.2,3,4,5,6; Xu, X. Q.2; Li, N. M.1; Liu, X. J.3,4; Liu, X.4; Xu, J. C.3,4; Feng, W.3,4; Liu, J. B.4; Gao, S. L.3,4; Liu, S. C.4
刊名	NUCLEAR FUSION
	2020-08-01
卷号	60
关键词	divertor heat flux width BOUT plus plus EAST LHW NB
ISSN号	0029-5515
DOI	10.1088/1741-4326/ab70d6
通讯作者	Xu, X. Q.(xu2@llnl.gov)
英文摘要	The BOUT++ edge plasma transport code is applied to study the effects of neutral recycling, drifts and heating scheme on edge plasma profiles and the divertor heat flux width of two discharges of the experimental advanced superconducting tokamak (EAST) steady-state H-mode plasmas heated by low hybrid wave (LHW) and neutral beam (NB), respectively. Neutral recycling seems to have played an important role in the plasma density profile. The edge plasma density drops dramatically for the case w/o neutral recycling, while it can be sustained for the case w/ neutral recycling. Drifts are found to have significant influences on edge plasma profiles. Both the amplitude and width of the divertor heat flux are found to have increased a lot due to drifts. The simulated heat flux width w/ drifts for the two discharges shows reasonable agreement with the experiments. However, the width from the simulation and experiment for the LHW heated discharge is much larger than that of the NB heated discharge. Comparison with Goldston's drift-based model and more detailed analysis on the heat flux contributions from drifts versus turbulence show that drifts are the dominant factor in edge plasma transport for both LHW and NB heated discharges, while turbulence may have played a more important role in determining the heat flux width in LHW heated discharges than that in NB heated discharges. This may account for the larger heat flux width in the LHW heated discharge. The magnetic topology and the equilibrium change by the LHW power may also be a potential reason for the larger heat flux width in the LHW heated discharges, which still needs more evidence and studies to support it. Additional SOLPS simulation w/o drifts for the two discharges show reasonable agreement with the counterpart from the BOUT++ simulation, suggesting the two are both suitable codes for EAST edge plasma simulation.
资助项目	National Natural Science Foundation of China[11975271] ; National Natural Science Foundation of China[11575236] ; National Natural Science Foundation of China[11675211] ; National Natural Science Foundation of China[11575235] ; National Natural Science Foundation of China[11405213] ; National Natural Science Foundation of China[11875294] ; National Magnetic Confinement Fusion Science Program of China[2014GB106000] ; National Magnetic Confinement Fusion Science Program of China[2014GB106005] ; National Magnetic Confinement Fusion Science Program of China[2015GB101000] ; National Magnetic Confinement Fusion Science Program of China[2015GB110001] ; National Key Research and Development Program of China[2017YFA0402500] ; National Key Research and Development Program of China[2017YFE0300500] ; National Key Research and Development Program of China[2017YFE0300501] ; China Scholarship Council (CSC)[201706340070] ; U.S. Department of Energy by Lawrence Livermore National Laboratory (LLNL)[DE-AC52-07NA27344] ; AHNFS[1808085J07]
WOS关键词	SOL WIDTH ; L-MODE ; PARTICLE ; PLASMAS ; POWER
WOS研究方向	Physics
语种	英语
出版者	IOP PUBLISHING LTD
WOS记录号	WOS:000555364200001
资助机构	National Natural Science Foundation of China ; National Magnetic Confinement Fusion Science Program of China ; National Key Research and Development Program of China ; China Scholarship Council (CSC) ; U.S. Department of Energy by Lawrence Livermore National Laboratory (LLNL) ; AHNFS
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/70884]
专题	中国科学院合肥物质科学研究院
通讯作者	Xu, X. Q.
作者单位	1.Dalian Univ Technol, Sch Phys, Dalian 116024, Peoples R China 2.Lawrence Livermore Natl Lab, Livermore, CA 94550 USA 3.Univ Sci & Technol China, Hefei 230026, Peoples R China 4.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 5.Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China 6.Shenzhen Univ, Coll Phys & Optoelect Engn, Shenzhen 518060, Peoples R China
推荐引用方式 GB/T 7714	Deng, G. Z.,Xu, X. Q.,Li, N. M.,et al. Simulation of divertor heat flux width on EAST by BOUT plus plus transport code[J]. NUCLEAR FUSION,2020,60.
APA	Deng, G. Z..,Xu, X. Q..,Li, N. M..,Liu, X. J..,Liu, X..,...&Wang, L..(2020).Simulation of divertor heat flux width on EAST by BOUT plus plus transport code.NUCLEAR FUSION,60.
MLA	Deng, G. Z.,et al."Simulation of divertor heat flux width on EAST by BOUT plus plus transport code".NUCLEAR FUSION 60(2020).