Title :
Hardwired control system changes for NSTX DC power feeds
Author :
Ramakrishnan, Shankar ; Xin Zhao ; Neumeyer, C. ; Lawson, J. ; Hatcher, R. ; Mozulay, R. ; Baker, Edwards ; Que, W.
Author_Institution :
Princeton Plasma Phys. Lab., Princeton, NJ, USA
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.
Keywords :
Tokamak devices; fusion reactor design; physical instrumentation control; plasma toroidal confinement; NSTX DC power feeds; NSTX DC power loop control; NSTX Upgrade; National Spherical Torus Experiment design; PLC-based system; Princeton Plasma Physics Laboratory; Tokamak Fusion Test Reactor; auxiliary subsystems; control logic; electromechanical relays; hardwired control system changes; Coils; Power supplies; Rectifiers; Relays; Safety; Standards;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635282