托卡马克撕裂模式的径向识别

J. Berrino, S. Cirant, G. DiAntona, E. Lazzaro
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引用次数: 0

摘要

目前研究的重点是热核等离子体中低螺旋模数(m,n)旋转磁岛的控制。这些扰动与电流剖面的局部扭曲有关,这可能是导致等离子体约束退化的严重原因。通过恢复未扰动的电流剖面,岛屿的宽度减小或完全被抑制。电流可以由岛上射频功率的沉积来驱动。传统的磁流体动力学(MHD)不稳定性是通过外部磁信号来监测的,然而,这些信号不能提供关于等离子体内部扰动的径向位置的信息。由于温度波动也与MHD不稳定性有关,因此ECE(电子回旋发射)信号可以提供有关当地电子温度的信息,用于识别岛屿的位置。在这里,我们描述了一个实时诊断/控制装置的设计,该装置使用原始算法进行有效的控制动作,包括“实时”识别相关状态变量(径向位置、岛幅、频率和相位),并相应地改变控制变量(波束功率调制和转向角)。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Radial identification of tearing modes in a Tokamak
The focus of the present research is the control of rotating magnetic islands of low helical mode numbers (m,n) in thermonuclear plasmas. These perturbations are associated with local distortions of the current profile that can be a serious cause of degradation of the plasma confinement. The islands are reduced in width or completely suppressed by restoring the unperturbed current profile. The current can be driven by the deposition of radio frequency power within the island. Traditionally magneto-hydrodynamic (MHD) instabilities are monitored by external magnetic signals that however give no information about the radial location of the perturbation within the plasma. Because temperature fluctuation is also associated with MHD instabilities, ECE (electron cyclotron emission) signals that give information about local electron temperature, are used to identify the islands position. Here, we describe the design of a real time diagnostics/control device using an original algorithm for an effective control action that involves identification of relevant state variables (radial location, island amplitude, frequency and phase) in "real time" and varies accordingly the control variables (wave beam power modulation and steering angles).
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