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Dynamic diagnostics of the error fields in tokamaks

机译：托卡马克中错误字段的动态诊断

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摘要

The error field diagnostics based on magnetic measurements outside the plasma is discussed. The analysed methods rely on measuring the plasma dynamic response to the finite-amplitude external magnetic perturbations, which are the error fields and the pre-programmed probing pulses. Such pulses can be created by the coils designed for static error field correction and for stabilization of the resistive wall modes, the technique developed and applied in several tokamaks, including DIII-D and JET. Here analysis is based on the theory predictions for the resonant field amplification (RFA). To achieve the desired level of the error field correction in tokamaks, the diagnostics must be sensitive to signals of several Gauss. Therefore, part of the measurements should be performed near the plasma stability boundary, where the RFA effect is stronger. While the proximity to the marginal stability is important, the absolute values of plasma parameters are not. This means that the necessary measurements can be done in the diagnostic discharges with parameters below the nominal operating regimes, with the stability boundary intentionally lowered. The estimates for ITER are presented. The discussed diagnostics can be tested in dedicated experiments in existing tokamaks. The diagnostics can be considered as an extension of the 'active MHD spectroscopy' used recently in the DIII-D tokamak and the EXTRAP T2R reversed field pinch.
机译：讨论了基于等离子体外部磁测量的误差场诊断。分析的方法依赖于测量等离子体对有限幅度外部磁扰动的动态响应，这是误差场和预编程的探测脉冲。这种脉冲可以由设计用于静态误差场校正和稳定电阻壁模式的线圈产生，这种技术已在包括DIII-D和JET在内的多种托卡马克中开发和应用。这里的分析是基于对共振场放大（RFA）的理论预测。为了在托卡马克中达到所需的误差场校正水平，诊断必须对几个高斯信号敏感。因此，部分测量应在等离子体稳定性边界附近进行，RFA效应较强。尽管接近边缘稳定性很重要，但血浆参数的绝对值并不重要。这意味着可以在诊断放电中以低于额定工作状态的参数进行必要的测量，并有意降低稳定性边界。列出了ITER的估算值。可以在现有托卡马克机的专用实验中测试所讨论的诊断程序。诊断可以被认为是最近在DIII-D托卡马克和EXTRAP T2R反向场收缩中使用的“主动MHD光谱”的扩展。

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