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Abstracts |
P. Sichta, J. Dong, G. Oliaro, P. Roney(PPPL)
The National Spherical Torus Experiment (NSTX) is an innovative magnetic fusion device that was constructed by the Princeton Plasma Physics Laboratory in collaboration with the Oak Ridge National Laboratory, Columbia University, and the University of Washington at Seattle. NSTX [1] is operated by a collection of autonomous control systems, each built and maintained by the individual engineering subsystem^Rs personnel. Most of the subsystems interface with the Central Instrumentation and Control System (CIC), which uses the Experimental Physics and Industrial Control System (EPICS). Major functions of the CIC include Process Control [2], Real-time Plasma Control [3], Physics Data Acquisition [4], and Facility Synchronization. This paper will present a broad introduction to the architecture, hardware, and software of the NSTX CIC and subsystem controls.
[1] Y-K. M. Peng, 'National NSTX Research Program,' 41st Annual Meeting of the (APS) Division of Plasma Physics,Seattle, WA (1999).
[2] P. Sichta, J. Dong, ^QThe NSTX Central Instrumentation and Control System,' 18th Symposium on Fusion Engineering, Albuquerque, NM (1999).
[3] D. Gates et al., 'Initial Operation of the NSTX Plasma Control System,' 27th EPS Conference on Contr. Fusion and Plasma Physics, Budapest (2000).
[4] P. Roney et al.,'Computer and Network Infrastructure of NSTX,' to be presented at 19th Symposium on Fusion Energy, Atlantic City, NJ (2001).
{*} Work supported by US DOE contract DE-AC02-76-CH0-3073.
eCONF
C011127
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ICALEPCS 2001
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