BPX PF coil power system configuration studies

The Burning Plasma Experiment (BPX) poloidal field (PF) system is required to support a maximum plasma current of 10.6 MA while providing plasma position and shape control. The plasma shaping control scenarios of double null, asymmetrical single null, and limiter operations must be accommodated. The coil power is to be supplied by existing power supplies which are currently in use on the Tokamak Fusion Test Reactor (TFTR). The power supplies derive their power from two existing variable frequency TFTR motor generator sets. An additional requirement of the system is the ability to accommodate an upgrade of the maximum plasma current pulse from 10.6 MA to 11.8 MA with minimum impact on tokamak operation. The authors describe and analyze the various PF coil power system requirements, the switching circuits used to accomplish the required coil scenarios, and the optimal allocation of the TFTR power supplies to meet the base requirements and anticipated upgrade requirements. The results from the simulation studies which verify the operation of the PF power system design are also presented.<
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