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The equivalent currents method has proven to be particularly effective in the identification of plasma boundary in Tokamak fusion devices. Anyway, the ill‐posedness of the mathematical model to be inverted calls for the adoption of suitable regularization techniques to be adopted, in particular to reduce the influence of the measurement errors. In this paper the equivalent currents method is illustrated, together with some details on its application to the plasma identification. In addition, two algorithms for the optimal choice of the representation basis are presented, together with a discussion about the obtained numerical results.
© MCB UP Limited
2001
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