Plasma performance improvement with favourable Bt relative to unfavourable Bt in RF-heated H-mode plasmas in EAST

被引：9

作者：

Lin, X. ^{[1
,2
]}

Yang, Q. Q. ^{[1
]}

Xu, G. S. ^{[1
]}

Huang, J. ^{[1
]}

Gong, X. Z. ^{[1
]}

Wang, L. ^{[1
]}

Qian, J. P. ^{[1
]}

Zhang, B. ^{[1
]}

Garofalo, A. M. ^{[3
]}

Chen, R. ^{[1
]}

Jia, G. Z. ^{[1
]}

Ye, Y. ^{[4
]}

Lu, Z. Y. ^{[1
,2
]}

Chen, L. ^{[1
]}

Zang, Q. ^{[1
]}

Liu, H. Q. ^{[1
]}

Li, M. H. ^{[1
]}

Wang, Y. M. ^{[1
,2
]}

He, L. ^{[1
]}

Xu, J. C. ^{[1
]}

Yu, Y. W. ^{[1
]}

Lin, S. Y. ^{[1
]}

Duan, Y. M. ^{[1
]}

机构：

[1] Chinese Acad Sci, Inst Plasma Phys, HFIPS, Hefei 230031, Peoples R China

[2] Univ Sci & Technol China, Hefei 230026, Peoples R China

[3] Gen Atom, San Diego, CA 92186 USA

[4] Shenzhen Univ, Shenzhen 518060, Peoples R China

来源：

NUCLEAR FUSION | 2021年 / 61卷 / 02期

基金：

中国国家自然科学基金; 中国博士后科学基金;

关键词：

plasma performance improvement; favourable toroidal field; EAST; lower hybrid wave (LHW); DENSITY PROFILE; EDGE PLASMA; CONFINEMENT; TRANSPORT; REFLECTOMETRY; INSTABILITY; TURBULENCE; SYSTEM; SHEAR;

D O I：

10.1088/1741-4326/abcb27

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：

Significant improvement of plasma performance in high-confinement mode (H-mode) discharges with favourable toroidal field B-t, i.e. the ion backward difference B drift towards the primary X-point, has been widely observed in the EAST tokamak with pure radio-frequency heating in contrast to that with the unfavourable B-t. Statistical analysis indicates that plasma in the favourable B-t has higher core electron temperature, similar core ion temperature and relatively steeper pedestal density compared with that in the unfavourable B-t. The improvement in plasma performance is mainly contributed by the increase of core electron temperature in the favourable B-t. Further analysis indicates that the plasma with favourable B-t has much lower density and recycling in the scrape-off layer (SOL). Lower SOL density and recycling benefit the mitigation of parametric instability activity of lower hybrid wave (LHW), and thus facilitate the increase of core electron temperature in the favourable B-t. The performance improvement in the favourable B-t demonstrates to be more evident with high LHW power. Divertor local E-r x B drift which can increase the backflow particles from the divertor region to the upstream region could be partly responsible for the much higher SOL plasma density in unfavourable B-t. These findings could facilitate the application of LHW power on future large fusion devices, such as the China Fusion Engineering Test Reactor, to achieve high-performance steady-state operation.

引用

页数：14

共 11 条

[11] Kinetic equilibrium reconstruction for the NBI- and ICRH-heated H-mode plasma on EAST tokamak
Zheng, Zhen
Xiang, Nong
Chen, Jiale
Ding, Siye
Du, Hongfei
Li, Guoqiang
Wang, Yifeng
Liu, Haiqing
Li, Yingying
Lyu, Bo
Zang, Qing
PLASMA SCIENCE & TECHNOLOGY, 2018, 20 (06)

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