| ITER装置中等离子体旋转和反馈控制对电阻壁模影响的数值研究 |
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| 引用本文： | 曹琦琦,刘悦,王硕. ITER装置中等离子体旋转和反馈控制对电阻壁模影响的数值研究[J]. 物理学报, 2021, 0(4): 270-277 |
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| 作者姓名： | 曹琦琦 刘悦 王硕 |
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| 作者单位： | 大连理工大学物理学院;核工业西南物理研究院 |
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| 基金项目： | 国家自然科学基金(批准号:11875098,11805054);国家磁约束核聚变能发展研究专项(批准号:2017YFE0300501)资助的课题. |
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| 摘 要： | 在托卡马克等离子体中,电阻壁模是非常重要的磁流体不稳定性,特征时间在毫秒量级.对长时间稳态运行下的先进托卡马克,电阻壁模限制着聚变装置的运行参数空间(放电时间和比压),影响经济效益,所以研究电阻壁模稳定性至关重要.本文使用MARS程序,针对ITER装置上9 MA先进运行平衡位形,研究了等离子体旋转和反馈控制对电阻壁模的...
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| 关 键 词： | 电阻壁模 等离子体环向旋转 反馈控制 |
Numerical study of effect of plasma rotation and feedback control on resistive wall mode in ITER |
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| Cao Qi-Qi,Liu Yue,Wang Shuo. Numerical study of effect of plasma rotation and feedback control on resistive wall mode in ITER[J]. Acta Physica Sinica, 2021, 0(4): 270-277 |
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| Authors: | Cao Qi-Qi Liu Yue Wang Shuo |
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| Affiliation: | (Key Laboratory of Materials Modification by Laser,Ion and Electron Beams,Ministry of Education,School of Physics,Dalian University of Technology,Dalian 116024,China;Southwestern Institute of Physics,Chengdu 610041) |
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| Abstract: | In tokamak plasmas,the resistive wall mode is a very important magnetohydrodynamic instability,and its time scale is on the order of millisecond.For the advanced tokamaks with long-pulse and steady-state operation,the resistive wall mode limits the operating parameter space(the discharge time and the radio of the plasma pressure to the magnetic pressure)of the fusion devices so that it affects the economic benefits.Therefore,it is very important to study the stability of the resistive wall modes in tokamaks.In this work,the influences of the plasma rotations and the feedback controls on the resistive wall modes are studied numerically using MARS code for an ITER 9 MA equilibrium designed for the advanced steady-state scenario.In the equilibrium,the profile of the safety factor has a weak negative magnetic shear in the core region.The safety factor is q0=2.44 on the magnetic axis and qα=7.13 on the plasma boundary.And,the minimum safety factor qmin is 1.60.The structure of this kind of weakly negative magnetic shear can generate higher radio of the plasma pressure to the magnetic pressure and it is the important feature of the advanced steady-state scenario.Using MARS code,for two cases:without wall and with ideal wall,the results of growth rates of the external kink modes for different values ofβN are obtained.The limit value ofβN^no-wall is 2.49 for the case without wall,and the limit value ofβN^ideal-wall is 3.48 for the case with ideal wall.Then,a parameter Cβ=(βN-βN^no-wall)/(βN^ideal-wall-βN^no-wall)is defined.The research results in this work show that with the plasma pressure scaling factor Cβ=0.7 and plasma rotation frequencyΩ0=1.1%ΩA,the resistive wall modes can be completely stabilized without feedback control.And,with the plasma pressure scaling factor Cβ=0.7 and the feedback gain|G|=0.6,only plasma rotation with the frequencyΩ0=0.2%ΩA can stabilize the resistive wall modes.Therefore,a faster plasma rotation is required to stabilize the resistive wall modes by the plasma flow alone.The synergetic effects of the feedback and the toroidal plasma flow on the stability of the RWM can reduce plasma rotation threshold,which satisfies the requirements for the operation of the advanced tokamaks.The conclusion of this work has a certain reference for the engineering design and the operation of CFETR. |
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| Keywords: | resistive wall mode plasma flow magnetic feedback |
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