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Analysis and Control of Spontaneous Currents in Rippled Tokamak Plasmas and Helical Plasmas

波纹托卡马克等离子体和螺旋等离子体自发电流的分析与控制

基本信息

批准号：
17560729
负责人：
NAKAMURA Yuji
金额：
$ 2.29万
依托单位：
Kyoto University
依托单位国家：
日本
项目类别：
Grant-in-Aid for Scientific Research (C)
财政年份：
2005
资助国家：
日本
起止时间：
2005 至 2007
项目状态：
已结题

来源：
https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-17560729/
关键词：
plasma fusion toroidal field ripple rippled tokamak helical plasma spontaneous current bootstrap current bumpy field component neoclassical transport theory

项目摘要

In magnetically confined toroidal plasmas with high plasma pressure, a spontaneous current, which called the bootstrap current, flows as is predicted by the neoclassical transport theory, and it gives an significant influence on the plasma confinement. The following studies have been done in order to investigate the effects of the bootstrap current on the plasma confinement theoretically, and to consider the methods to control the bootstrap current.1. Three dimensional MHD equilibrium code, HINT2, has been developed to calculate the MHD equilibrium of non-axisymmetric plasmas accurately. We also analyze the effect of the bumpy component of the plasma boundary shape on the MHD stability.2. In the experiments of an L=1 heliotron device, Heliotron J, it is demonstrated that the direction of the bootstrap current can be reversed when the magnetic configuration is varied. We did the theoretical analysis of the bootstrap current in L=1 heliotron plasmas and in rippled tokamak plasmas, and clarified the dependence of the magnetic configuration and the toroidal field ripple on the bootstrap current.3. The integrated simulations of the plasma current profile including the beam driven current and the bootstrap current have been done with the consistent MHD equilibrium calculation. For this purpose, numerical program which analyze the bootstrap current and beam driven current has been modularized, and the module which simulate the time evolution of the plasma current profile in non-axisymmetric toroidal plasmas has been developed. We clarified the mechanism of the transient response of the plasma current profile in LHD plasma experiments.

在具有高等离子体压力的磁约束环形等离子体中，如新经典输运理论所预言的那样，会有一种称为自举电流的自发电流流动，它对等离子体的约束有重要影响。为了从理论上研究自举电流对等离子体约束的影响，并考虑控制自举电流的方法，进行了以下研究。为了精确计算非轴对称等离子体的MHD平衡，开发了三维MHD平衡程序Hint2。我们还分析了等离子体边界形状的起伏分量对MHD稳定性的影响。在L=1氦加速器装置--氦J的实验中，证明了磁位形改变时，自举电流的方向可以反转。对L=1氦加速器等离子体和波纹托卡马克等离子体中的自举电流进行了理论分析，阐明了磁位形和环向场纹波与自举电流的关系。采用一致的MHD平衡计算方法，对包括束流驱动电流和自举电流在内的等离子体电流分布进行了整体模拟。为此，对分析自举电流和束流驱动电流的数值程序进行了模块化，并开发了模拟非轴对称环形等离子体中等离子体电流分布随时间演化的模块。阐明了LHD等离子体实验中等离子体电流分布的暂态响应机制。