Hardwired Control Changes For NSTX DC Power Feeds
Authors: S. Ramakrishnan, Xin Zhao, C. Neumeyer, J. Lawson, R. Hatcher, R. Mozulay, E. Baker, W. Que
Abstract:
The National Spherical Torus Experiment (NSTX) has been
designed and installed in the existing facilities at Princeton Plasma
Physics 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. The original TFTR Hardwired
Control System (HCS) with electromechanical relays was used for
NSTX DC Power loop control and protection during NSTX
operations. As part of the NSTX Upgrade, the HCS is being changed
to a PLC-based system with the same control logic. This paper gives
a description of the changeover to the new PLC-based system
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Submitted to: SOFE 2013 Proeedings (June 0213) 25th Symposium on Fusion Engineering, San Francisco, CA (June 10-14, 2013)
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Download PPPL-4921 (pdf 1 KB 4 pp)
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