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Plasma shape control on the National Spherical Torus Experiment (NSTX) using real-time equilibrium reconstruction

机译:使用实时平衡重建对国家球形圆环实验(NSTX)进行等离子体形状控制

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Plasma shape control using real-time equilibrium reconstruction has been implemented on the National Spherical Torus Experiment (NSTX). The rtEFIT code originally developed for use on DM-D was adapted for use on NSTX The real-time equilibria provide calculations of the flux at points on the plasma boundary, which are used as input to a shape control algorithm known as isoflux control. The flux at the desired boundary location is compared with a reference flux value, and this flux error is used as the basic feedback quantity for the poloidal field coils on NSTX. The hardware that comprises the control system is described, as well as the software infrastructure. Examples of precise boundary control are also presented.
机译:在国家球形圆环实验(NSTX)上已经实现了使用实时平衡重建的等离子体形状控制。最初开发用于DM-D的rtEFIT代码适合用于NSTX。实时平衡提供了等离子边界上各点处的通量计算,这些计算用作形状控制算法(称为等通量控制)的输入。将所需边界位置处的通量与参考通量值进行比较,并将该通量误差用作NSTX上极向场线圈的基本反馈量。描述了组成控制系统的硬件以及软件基础结构。还介绍了精确边界控制的示例。

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