Power System for NSTX Upgrade
Authors: . Ramakrishnan, C. Neumeyer, J. Lawson, R. Mozulay, E. Baker, R. Hatcher, N. Desai, Weiguo Que, and Xin Zhao
Abstract:
This The National Spherical Torus Experiment
(NSTX) has been designed and installed in the existing facilities
at Princeton Plasma Physic Laboratory (PPPL). Most of the
hardware, plant facilities, auxiliary sub-systems, and power
systems originally used for the Tokamak Fusion Test Reactor
(TFTR) have been used with suitable modifications to reflect
NSTX needs. At present, the NSTX power system is feeding
thirteen (13) circuits from the Power converters. An upgrade of
the NSTX center stack is proposed. This entails a much higher
Toroidal Field Current from 71.2kA to 129.8kA, and requires
major configuration changes including doubling the number of
parallel strings of rectifiers along with associated power loop
changes. Also, three additional coils will be installed in the
machine. The control and protection of the rectifiers have to be
replaced to reflect state of the art features to enhance the
performance. This paper describes the details of the proposed
Power system for NSTX upgrade.
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Submitted to: 38th International Conference on Plasma Science & 24th Symposium on Fusion Engineering/ICOPS 2011 SOFE, Chicago, IL, June 26-30, 2011
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Download PPPL-4673 (pdf 184 KB 5 pp)
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