低混杂波高N‖分量对EAST等离子体电流驱动的影响

计算物理 ›› 2020, Vol. 37 ›› Issue (4): 467-472.

低混杂波高N_‖分量对EAST等离子体电流驱动的影响

刘祖光¹, 李新霞^1,2, 杨明¹

1. 南华大学核科学技术学院, 湖南衡阳 421001;
2. 中国科学院等离子体物理研究所, 安徽合肥 230031

收稿日期:2019-06-05 修回日期:2019-09-11 出版日期:2020-07-25 发布日期:2020-07-25
作者简介:刘祖光(1994-),男,硕士研究生,主要从事核聚变与等离子体物理研究,E-mail:970621150@qq.com
基金资助:
国家重点研发计划（2017YFE0300406）及国家自然科学基金（11775108）资助项目

Effect of Lower Hybrid Wave Current Drive with High Component N_‖ on EAST

LIU Zuguang¹, LI Xinxia^1,2, YANG Ming¹

1. School of Nuclear Science and Technology, University of South China, Hengyang, Hunan 421001, China;
2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui 230031, China

Received:2019-06-05 Revised:2019-09-11 Online:2020-07-25 Published:2020-07-25

摘要/Abstract

摘要： EAST等离子体高约束模运行条件下，在等离子体边缘区域观测到明显的等离子体电流带.在EAST托卡马克装置非圆截面平衡位形下，使用射线追踪方法研究低混杂波高平行折射率N_‖分量对电流驱动的影响.结果表明：当-8≤N_‖≤-6时，平行折射率分量能够在小半径（0.7 < r/a < 1）区域驱动kA量级的等离子体电流.对于具有台基区、等离子体边缘温度更高的电子温度剖面，驱动电流的位置r/a>0.9.低混杂波朗道阻尼的理论分析与数值模拟结果一致.另外，高N_‖低混杂波在等离子体边缘的功率沉积和电流驱动与电子温度分布和发射谱分布相关.

关键词: 低混杂波电流驱动, 托卡马克, 等离子体电流

Abstract: In EAST tokamak high confinement mode discharge, a plasma current belt was found experimentally at the edge plasmas region. For EAST plasma with non-circular cross-section equilibrium configuration, effect of high parallel refractive index N_‖ component of lower hybrid wave on current drive was numerically studied. Results of the ray-tracing platform shows that kA plasma current emerges in a region of normalized radius from 0.7 to 1.0 for 6≤N_‖≤8. For electron temperature profile with pedestal and higher plasma edge temperature, the region of drive current is r/a>0.9.A theoretical analysis of lower hybrid Landau damping in EAST tokamak was also performed. Effects of electron density profile and formation of lower hybrid wave spectrum on current drive were discussed.

Key words: lower hybrid current drive, tokamak, plasma current

中图分类号:

O532

刘祖光, 李新霞, 杨明. 低混杂波高N_‖分量对EAST等离子体电流驱动的影响[J]. 计算物理, 2020, 37(4): 467-472.

LIU Zuguang, LI Xinxia, YANG Ming. Effect of Lower Hybrid Wave Current Drive with High Component N_‖ on EAST[J]. CHINESE JOURNAL OF COMPUTATIONAL PHYSICS, 2020, 37(4): 467-472.

参考文献

[1] FISCH N J. Confining a tokamak plasma with rf-driven currents[J]. Physical Review Letters, 1978, 41(13):873-876.
[2] IDE S, TEAM T J. Overview of JT-60U progress towards steady-state advanced tokamak[J]. Nuclear Fusion, 2005, 45(10):S48-S62.
[3] DUAN W X, WU B. Simulation of lower hybrid wave power deposition and current drive control in EAST[J]. Chinese Journal of Computational Physics, 2011, 28(3):438-444.
[4] HOANG G T, BÉCOULET A, JACQUINOT J, et al. A lower hybrid current drive system for ITER[J]. Nuclear Fusion, 2009, 49(7):075001.
[5] LI J, WAN B N. Recent progress in RF heating and long-pulse experiments on EAST[J]. Nuclear Fusion, 2011, 51(9):094007.
[6] LU B, HUANG M, ZENG H, et al. Development of the 3.7 GHz LHCD system on HL-2A[J]. Journal of the Korean Physical Society, 2014, 65(8):1243-1246.
[7] DUAN X R, LIU Y, XU M, et al. Overview of recent HL-2A experiments[J]. Nuclear Fusion, 2017, 57(10):102013.
[8] QIAN J, GONG X, WAN B N, et al. Integrated operating scenario to achieve 100-second, high electron temperature discharge on EAST[J]. Plasma Science and Technology, 2016, 18(5):457-459.
[9] LI Y L, XU G S, WU Z W, et al. Hot spots induced by LHCD in the shadow of antenna limiters in the EAST tokamak[J]. Physics of Plasmas, 2018, 25(8):082503.
[10] GONICHE M, MAILLOUX J, DEMERS Y, et al. Strong toroidal asymmetries in power deposition on divertor and first wall components during LHCD on TdeV and Tore Supra[J]. Journal of Nuclear Materials,1997, 241:745-749.
[11] JACQUET P, COLAS L, MAYORAL M L, et al. Heat loads on JET plasma facing components from ICRF and LH wave absorption in the SOL[J]. Nuclear Fusion, 2011, 51(10):532-542.
[12] IGNAT D, VALEO E, JARDIN S. Dynamic modelling of lower hybrid current drive[J]. Nuclear Fusion, 1994, 34(6):837-852.
[13] HE Q B, TANG Y, MU Z Z. Numerical method of simulating low hybrid wave current drive[J]. Chinese Journal of Computational Physics, 1996, 13(02):159-166.
[14] ZHANG G R, KUANG G L. Numerical investigation on synergistic effect between IBW and LHW in HT-7 tokamak[J]. Chinese Journal of Computational Physics, 2006, 23(3):325-334.
[15] GOLANT V E. Plasma penetration near the lower hybrid frequency[J]. Soviet Physics Technical Physics, 1972, 16:1980-1988.
[16] LI X X, XIANG N, GAN C Y. Effect of wave accessibility on lower hybrid wave current drive in experimental advanced superconductor tokamak with H-mode operation[J]. Chinese Physics Letters, 2015, 32(3):035202.
[17] LITAUDON X, ARSLANBEKOV R, HOANG G T, et al. Stationary magnetic shear reversal experiments in Tore Supra[J]. Plasma Physics and Controlled Fusion, 1999, 38(9):1603-1626.
[18] LI M H, DING B J, LIU F K, et al. Lower hybrid current drive experiments with different launched wave, frequencies in the EAST tokamak[J]. Physics of Plasmas, 2016, 23(10):102512.