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Recently, various kinds of extreme exciting conditions, such as the ac-dc hybrid excitation, are applied to transformers, reactors etc. with the development of the HVDC system. The modeling and estimation of stray-field losses are of increasingly importance in the electromagnetic design of such devices, and it is challenging to measurement and numerical analysis.
The National Spherical Torus Experiment (NSTX) is undergoing a significant upgrade. The upgrade increases the toroidal field and pulse length, adds three new diverter coils and a second neutral beam injection (NBI) system. The magnet coil power supply systems for the NSTX have been redesigned with many modifications to reflect NSTX upgrade needs. The NSTX power supply system includes three major parts...
The stellarator fusion experiment Wendelstein 7-X (W7-X) is currently under construction at the Max-PlanckInstitut für Plasmaphysik in Greifswald (IPP), Germany. Five normal conducting trim coils have been designed to allow for fine tuning of the main magnetic field during plasma operation. To limit the mechanical stress in the coil the proper function of the coil cooling system must be carefully...
NSTX at Princeton Plasma Physics Laboratory (PPPL) requires sophisticated plasma positioning control system for stable plasma operation. TF magnetic coils and PF magnetic coils provide electromagnetic fields to position and shape the plasma vertically and horizontally respectively. NSTX utilizes twenty six coil power supplies to establish and initiate electromagnetic fields through the coil system...
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