Calculation of the Heat Flux on the First Wall During Disruption on Tokamak

doi:10.1007/s10894-016-0118-6

	Calculation of the Heat Flux on the First Wall During Disruption on Tokamak
	Yang, Zhendong 1,2; Shu, Shuangbao 3; Gan, Kaifu2 ; Fang, Jianan 4; Zhang, Bin2
	2017-02-01
发表期刊	JOURNAL OF FUSION ENERGY
摘要	Disruptions are the most dangerous instabilities in tokamak plasma. During plasma disruption, the large amounts of energy will be deposited on Plasma Facing Components (PFCs) which is a damaging threat for the divertor target and the first wall materials. Therefore, studying the characteristic of heat deposition on the first wall is very significant. The Infrared (IR) camera is an effective tool to measure the surface temperature profile on the first wall on the Experimental Advanced Superconducting Tokamak (EAST). With a finite difference method, the heat flux arrived to the divertor can be calculated from the surface temperature. However, the surface layer on the divertor has a great influence on the calculation of the heat flux on the divertor. The numerical method for solving heat conduction for semi-infinite model is given in this paper. And the thermal resistance of surface layers is considered in this numerical method. In addition, the distribution of heat flux on the divertor during disruption is also shown.
文章类型	Article
关键词	Infrared Camera Tokamak Plasma Disruption Heat Flux
WOS标题词	Science & Technology ; Technology
DOI	10.1007/s10894-016-0118-6
关键词[WOS]	JET
收录类别	SCI
语种	英语
项目资助者	National Natural Science Foundation of China(11105028) ; National Natural Science Foundation of China(11105028) ; National Natural Science Foundation of China(11105028) ; National Natural Science Foundation of China(11105028) ; National Natural Science Foundation of China(11105028) ; National Natural Science Foundation of China(11105028) ; National Natural Science Foundation of China(11105028) ; National Natural Science Foundation of China(11105028) ; National Magnetic Confinement Fusion Science Program of China(2013GB102001 ; National Magnetic Confinement Fusion Science Program of China(2013GB102001 ; National Magnetic Confinement Fusion Science Program of China(2013GB102001 ; National Magnetic Confinement Fusion Science Program of China(2013GB102001 ; National Magnetic Confinement Fusion Science Program of China(2013GB102001 ; National Magnetic Confinement Fusion Science Program of China(2013GB102001 ; National Magnetic Confinement Fusion Science Program of China(2013GB102001 ; National Magnetic Confinement Fusion Science Program of China(2013GB102001 ; 2015GB102004) ; 2015GB102004) ; 2015GB102004) ; 2015GB102004) ; 2015GB102004) ; 2015GB102004) ; 2015GB102004) ; 2015GB102004)
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000392833200003
引用统计	被引频次：2[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.hfcas.ac.cn:8080/handle/334002/31672
专题	中科院等离子体物理研究所
作者单位	1.Tongling Univ, Tongling 244000, Anhui, Peoples R China 2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 3.Hefei Univ Technol, Sch Instrument Sci & Optoelect Engn, Hefei 230009, Peoples R China 4.Donghua Univ, Coll Sci, Shanghai 201620, Peoples R China
第一作者单位	中科院等离子体物理研究所
推荐引用方式 GB/T 7714	Yang, Zhendong,Shu, Shuangbao,Gan, Kaifu,et al. Calculation of the Heat Flux on the First Wall During Disruption on Tokamak[J]. JOURNAL OF FUSION ENERGY,2017,36(1):15-20.
APA	Yang, Zhendong,Shu, Shuangbao,Gan, Kaifu,Fang, Jianan,&Zhang, Bin.(2017).Calculation of the Heat Flux on the First Wall During Disruption on Tokamak.JOURNAL OF FUSION ENERGY,36(1),15-20.
MLA	Yang, Zhendong,et al."Calculation of the Heat Flux on the First Wall During Disruption on Tokamak".JOURNAL OF FUSION ENERGY 36.1(2017):15-20.

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