Recent Results of LHCD Experiments in EAST

DING Bojiang; KONG Erhua; LI Miaohui; QIN Yongliang; ZHANG Lei; A. EKEDAHL; Y. PEYSSON; WANG Mao; XU Handong; HU Huaichuan; HUANG Yiyun; XU Guosheng; SHAN Jiafang; LIU Fukun; ZHAO Yanping; GAO Xiang

Plasma Science and Technology > 2011 > 13(2): 153-156.

DING Bojiang, KONG Erhua, LI Miaohui, QIN Yongliang, ZHANG Lei, A. EKEDAHL, Y. PEYSSON, WANG Mao, XU Handong, HU Huaichuan, HUANG Yiyun, XU Guosheng, SHAN Jiafang, LIU Fukun, ZHAO Yanping, GAO Xiang. Recent Results of LHCD Experiments in EAST[J]. Plasma Science and Technology, 2011, 13(2): 153-156.

Citation:

PDF (242 KB)

Recent Results of LHCD Experiments in EAST

Funds: supported by National Natural Science Foundation of China (Nos. 10875149, 10928509), the National Magnetic Confinement Fusion Science Program of China (No. 2010GB105004), the Core University Program between Japan and China, and the Dean Foundation of Hefei Institute of Physical Science, Chinese Academy of Science.

More Information

Graphical Abstract

Abstract

Abstract

Lower hybrid wave (LHW)-plasma coupling and lower hybrid current drive (LHCD) experiments in divertor, including single-null and double-null, and limiter configurations were conducted systematically in EAST. A maximum power for launched LHW is 1.4 MW and the plasma current with LHCD is about 1 MA. It is indicated that the coupling is best in limiter configuration, then in single-null one, while worst in double-null one. Study in current drive efficiency by a least squares fit shows that there is no obvious difference in drive efficiency between the double-null and the single-null cases, whereas the efficiency is a slightly lower in the limiter case. The effect of plasma density on the current drive efficiency is due to the influence of density on impurity concentration.
- LHCD,
- LHW-plasma coupling,
- configuration

FullText(HTML)

References (0)

[1]	Wenjia WANG (王文家), Deng ZHOU (周登), Yue MING (明玥). The residual zonal flow in tokamak plasmas with a poloidal electric field[J]. Plasma Science and Technology, 2019, 21(1): 15101-015101. DOI: 10.1088/2058-6272/aadd8e
[2]	Wei YOU (尤玮), Hong LI (李弘), Wenzhe MAO (毛文哲), Wei BAI (白伟), Cui TU (涂翠), Bing LUO (罗兵), Zichao LI (李子超), Yolbarsop ADIL (阿迪里江), Jintong HU (胡金童), Bingjia XIAO (肖炳甲), Qingxi YANG (杨庆喜), Jinlin XIE (谢锦林), Tao LAN (兰涛), Adi LIU (刘阿娣), Weixing DING (丁卫星), Chijin XIAO (肖持进), Wandong LIU (刘万东). Design of the poloidal field system for KTX[J]. Plasma Science and Technology, 2018, 20(11): 115601. DOI: 10.1088/2058-6272/aac8d5
[3]	Xudong WANG (王旭东), Liuwei XU (许留伟), Peng FU (傅鹏), Ji LI (李冀), Yanan WU (吴亚楠). Harmonics analysis of the ITER poloidal field converter based on a piecewise method[J]. Plasma Science and Technology, 2017, 19(12): 125602. DOI: 10.1088/2058-6272/aa86a5
[4]	YUAN Hongwen (袁红文), FU Peng (傅鹏), GAO Ge (高格), HUANG Liansheng (黄连生), SONG Zhiquan (宋执权), HE Shiying (何诗英), WU Yanan (吴亚楠), DONG Lin (董琳), WANG Min (王敏), FANG Tongzhen (房同珍). On the Sequential Control of ITER Poloidal Field Converters for Reactive Power Reduction[J]. Plasma Science and Technology, 2014, 16(12): 1147-1152. DOI: 10.1088/1009-0630/16/12/11
[5]	LI Jinchao(李金超), Song Zhiquan(宋执权), XU Liuwei(许留伟), FU Peng(傅鹏), GUO Bin(郭斌), LI Sen(李森), DONG Lin(董琳), WANG Min(王敏). Current Sharing Analysis of Arm Prototype for ITER PF Converter Bridge[J]. Plasma Science and Technology, 2014, 16(3): 283-287. DOI: 10.1088/1009-0630/16/3/20
[6]	LI Weixin (李炜昕), YUAN Zhensheng (袁振圣), WU Wenjing (武文晶), CHEN Zhenmao (陈振茂). Numerical Analysis on the Magneto-Elastic Stability of Current -Carrying Conductors: Aiming at Applications for the Tokamak System[J]. Plasma Science and Technology, 2013, 15(2): 175-178. DOI: 10.1088/1009-0630/15/2/20
[7]	ZHU Zhe (朱哲), ZHU Yinfeng (朱银锋), HUANG Ronglin (黄荣林), FU Peng (傅鹏), DING Yixiao(丁逸骁). Study on the Current-sharing Control System of the TF Power Supply for a Superconducting Tokamak[J]. Plasma Science and Technology, 2012, 14(10): 941-946. DOI: 10.1088/1009-0630/14/10/16
[8]	Long Feng(龙风), Liu Fang(刘方), Wu Yu(武玉), Ni Zhipeng(倪志鹏). The First Benchmarking of ITER BR Nb3Sn Strand of CNDA[J]. Plasma Science and Technology, 2012, 14(9): 847-849. DOI: 10.1088/1009-0630/14/9/14
[9]	CHEN Peng, FU Peng, SONG Zhiquan. An Improvement on Current Sharing Characteristics of Poloidal Field (PF) AC-DC Converters[J]. Plasma Science and Technology, 2011, 13(4): 497-501.
[10]	LIU Bo, WU Yu. Test and Analysis of China's First Short Conductor Sample for ITER Toroidal Field Coils[J]. Plasma Science and Technology, 2011, 13(1): 106-110.