Optimization of helicon wave off-axis current drive in CFETR tokamak

doi:10.1016/j.fusengdes.2021.112897

HFCAS OpenIR

	Optimization of helicon wave off-axis current drive in CFETR tokamak
	Li, Xinxia1,2 ; Li, Guozhuang 1; Liu, Hongbo 1,3
	2021-11-01
发表期刊	FUSION ENGINEERING AND DESIGN
ISSN	0920-3796
通讯作者	Li, Xinxia(li_xx@usc.edu.cn)
摘要	The China Fusion Engineering Testing Reactor (CFETR) is a tokamak reactor and aims to eventually reach DEMO relevant fusion power level of 1 GW. A lower single null configuration of the divertor design is proposed for the machine. To obtain the high performance operation of the plasma, both the hybrid and steady-state operating scenarios are suggested. In these scenarios, the plasma beta of similar to 1.6% has been generally reached. In the paper, helicon wave propagation and current drive in CFETR are studied through GENRAY/CQL3D code. An analysis of the wave damping factor in CFETR plasma indicates that the electron Landau damping is dominant for the core plasma. According to the dimensionless parameter xi(e) and beta(e), a strong wave damping region is found. Based on the GENRAY simulation, the single pass power absorptions are generally obtained in both scenarios. Scanning of generated current on the launched poloidal angle indicates that high current drive efficiency is produced at theta similar to 30 degrees. For helicon wave with frequency f = 700 MHz, calculations of the current drive show that off-axis current drive about 30 kA/MW and 50 kA/MW are obtained in the hybrid and steady-state scenarios respectively. Simultaneously, the lower plasma density and high temperature promote the high current generation. Moreover, the obtained current drive and its peak position are shown to be sensitive to the launched n(//) similar to Finally, the helicon wave with frequency f = 700 MHz and launched n(//) similar to 2.0-3.0 is proposed to be a promising scheme for effective off-axis current drive in CFETR.
关键词	Tokamak CFETR Helicon wave Plasma current drive
DOI	10.1016/j.fusengdes.2021.112897
关键词[WOS]	SCENARIOS ; RECONSTRUCTION ; PARAMETERS ; SYSTEM
收录类别	SCI
语种	英语
资助项目	National Natural Science Foundation of China[11775108] ; National Key R&D Program of China[2017YFE0300406]
项目资助者	National Natural Science Foundation of China ; National Key R&D Program of China
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000706528200001
出版者	ELSEVIER SCIENCE SA
引用统计	被引频次：3[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/334002/125654
专题	中国科学院合肥物质科学研究院
通讯作者	Li, Xinxia
作者单位	1.Univ South China, Dept Nucl Phys, Hengyang 421001, Peoples R China 2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 3.HengYang Normal Univ, Coll Phys & Elect Engn, Hengyang 421008, Peoples R China
第一作者单位	中科院等离子体物理研究所
通讯作者单位	中科院等离子体物理研究所
推荐引用方式 GB/T 7714	Li, Xinxia,Li, Guozhuang,Liu, Hongbo. Optimization of helicon wave off-axis current drive in CFETR tokamak[J]. FUSION ENGINEERING AND DESIGN,2021,172.
APA	Li, Xinxia,Li, Guozhuang,&Liu, Hongbo.(2021).Optimization of helicon wave off-axis current drive in CFETR tokamak.FUSION ENGINEERING AND DESIGN,172.
MLA	Li, Xinxia,et al."Optimization of helicon wave off-axis current drive in CFETR tokamak".FUSION ENGINEERING AND DESIGN 172(2021).