Magnetic field map in magnetically confined thermonuclear fusion devices must be carefully controlled, in order to achieve desired performance. Residual error fields, which are in any case present, must be reduced using suitably designed “additional” coils. Since the feeding currents in coils for shape and position control are time-varying, also correction currents waveform must be optimized to achieve best performance. In this paper, the optimization of shape and power supply waveforms of such additional coils is tackled, with reference to FAST Tokamak

Optimal Design of Correction Coils in Tokamak Fusion Devices

CHIARIELLO, Andrea Gaetano;FORMISANO, Alessandro;MARTONE, Raffaele;
2014

Abstract

Magnetic field map in magnetically confined thermonuclear fusion devices must be carefully controlled, in order to achieve desired performance. Residual error fields, which are in any case present, must be reduced using suitably designed “additional” coils. Since the feeding currents in coils for shape and position control are time-varying, also correction currents waveform must be optimized to achieve best performance. In this paper, the optimization of shape and power supply waveforms of such additional coils is tackled, with reference to FAST Tokamak
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11591/167706
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