Study of intrinsic rotation by the Gyrokinetic Electromagnetic Numerical Experiment code in the Joint Texas Experimental Tokamak

被引:1
作者
Wang, Duoqin [1 ]
Yan, Wei [1 ]
Chen, Zhongyong [1 ,2 ]
Ye, Xin [1 ]
Li, Wei [1 ]
Yin, Zhiyang [1 ]
Hu, Jie [1 ]
Bai, Wei [1 ]
Zhong, Yu [1 ]
机构
[1] Huazhong Univ Sci & Technol, Sch Elect & Elect Engn, Int Joint Res Lab Magnet Confinement Fus & Plasma, State Key Lab Adv Electromagnet Engn & Technol, Wuhan 430074, Peoples R China
[2] Chengdu Univ, Chengdu 610106, Peoples R China
基金
中国国家自然科学基金; 中国博士后科学基金;
关键词
fusion plasma; plasma flows; plasma simulation; TOROIDAL ROTATION; PLASMA ROTATION; HIGH MODE; MOMENTUM; TEMPERATURE; SUPPRESSION; TURBULENCE; TRANSPORT; FIELD;
D O I
10.1017/S0022377820000343
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 core toroidal plasma intrinsic rotation has been studied by experiments and simulations in the Joint Texas Experimental Tokamak (J-TEXT). The direction of core intrinsic rotation in the J-TEXT plasma is counter-current. As the plasma density ramps up, the rotation velocity increases in the counter-current direction. By comparing four different electron densities, linear local gyrokinetic simulations have been performed by the Gyrokinetic Electromagnetic Numerical Experiment code for the first time on J-TEXT. It is found that the most dominant turbulence is the ion temperature gradient at 0:2a, where a is the minor radius of the plasma and this is unchanged during the plasma density ramp up. By scanning the radial wave vectors, it is found that the residual stress term reverses from negative to positive when the plasma density exceeds a certain threshold. The pinch term is larger than the residual stress term at all four electron densities, which means that the pinch term is always dominant in the core of a J-TEXT plasma.
引用
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页数:17
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