作者: V.D Pustovitov
DOI: 10.1088/0029-5515/47/7/007
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摘要: The error field diagnostics based on magnetic measurements outside the plasma is discussed. analysed methods rely measuring dynamic response to finite-amplitude external perturbations, which are fields and pre-programmed probing pulses. Such pulses can be created by coils designed for static correction stabilization of resistive wall modes, technique developed applied in several tokamaks, including DIII-D JET. Here analysis theory predictions resonant amplification (RFA). To achieve desired level must sensitive signals Gauss. Therefore, part should performed near stability boundary, where RFA effect stronger. While proximity marginal important, absolute values parameters not. This means that necessary done diagnostic discharges with below nominal operating regimes, boundary intentionally lowered. estimates ITER presented. discussed tested dedicated experiments existing tokamaks. considered as an extension 'active MHD spectroscopy' used recently tokamak EXTRAP T2R reversed pinch.