Lower hybrid current drive experiments and improved performance on the HT-7 superconducting tokamak

被引:51
作者
Kuang, GL [1 ]
Liu, YX [1 ]
Shan, JF [1 ]
Xu, WH [1 ]
Zhang, XQ [1 ]
Liu, DC [1 ]
Liu, FK [1 ]
Zhu, YB [1 ]
Zhang, C [1 ]
Zheng, GH [1 ]
Wu, JS [1 ]
Lin, JN [1 ]
Ding, BJ [1 ]
Xu, HD [1 ]
Fang, YD [1 ]
Li, JG [1 ]
Luo, JR [1 ]
Zhang, XD [1 ]
Wan, BN [1 ]
Zhao, QC [1 ]
Mao, JS [1 ]
Gao, X [1 ]
Zhang, SY [1 ]
Li, CF [1 ]
Gu, XM [1 ]
Qing, PJ [1 ]
Fan, HY [1 ]
Liu, SX [1 ]
Ling, BL [1 ]
Ding, BL [1 ]
Li, YH [1 ]
Wu, ZW [1 ]
Jie, YX [1 ]
Liu, S [1 ]
Xie, JK [1 ]
Wan, YX [1 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei, Peoples R China
关键词
D O I
10.1088/0029-5515/39/11Y/317
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The feedback control system to control plasma current and position on the HT-7 superconducting tokamak was greatly improved in early 1998. Lower hybrid current drive (LHCD) experiments with the improved control system were performed to sustain long pulse discharges and to improve plasma confinement. Partial non-inductive current drive and full non-inductive current drive for several seconds by means of LHCD were demonstrated. It was observed that plasma confinement could be considerably improved by LHCD. Experimental evidence suggests that this improvement during the LHCD phase could be due to the modification of the current profile in the outer region of the plasma. MHD modes (especially m = 2) seem unstable with such a current profile. The EFIT code was modified for the reconstruction of the magnetic surfaces in HT-7 and a test computation was performed.
引用
收藏
页码:1769 / 1774
页数:6
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