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性密闭的环形等离子体中，自发电流称为自举电流，如新古典传输理论所预测的，它对等离子体约束产生了重大影响。已经进行了以下研究，以研究自举电流对等离子体限制的影响，并考虑控制自举电流的方法1。已经开发了三维MHD平衡代码Hint2，以准确计算非轴对称等离子体的MHD平衡。我们还分析了等离子体边界形状的颠簸成分对MHD稳定性的影响2。在L = 1 Heliotron设备Heliotron J的实验中，可以证明，当磁性构型变化时，引导电流的方向可以逆转。我们对Bootstrap电流进行了L = 1 Heliotron等离子体的理论分析，并在带状的Tokamak等离子体中进行了理论分析，并阐明了磁构型的依赖性和环形场纹波对自举电流的依赖性。3。血浆电流轮廓的集成模拟（包括光束驱动电流和引导电流）已通过一致的MHD平衡计算进行。为此，分析引导电流和光束驱动电流的数值程序已被模块化，并且已经开发了模拟血浆电流谱的时间演化的模块，以非轴对称环形性等离子体的等离子体中开发出来。我们阐明了LHD等离子体实验中血浆电流轮廓的瞬时响应的机理。