DocumentCode
2113330
Title
The NSTX Central Instrumentation and Control System
Author
Sichta, P. ; Dong, J. ; Oliaro, G. ; Tindall, K.
Author_Institution
Plasma Phys. Lab., Princeton Univ., NJ, USA
fYear
1999
fDate
1999
Firstpage
292
Lastpage
295
Abstract
Earlier this year the National Spherical Torus experiment (NSTX) at the Princeton Plasma Physics Laboratory achieved “first plasma”. The Central Instrumentation and Control system was used to support plasma operations. Major elements of the system include the process control system, plasma control system, network system, data acquisition system, and synchronization system. This paper will focus on the process control system. Topics include the architecture, hardware interface, operator interface, data management, and system performance
Keywords
Tokamak devices; computerised control; fusion reactor design; nuclear engineering computing; process control; Central Instrumentation and Control System; NSTX; architecture; data management; hardware interface; operator interface; process control system; Centralized control; Control systems; Data acquisition; Hardware; Instruments; Laboratories; Physics; Plasmas; Process control; System performance;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1999. 18th Symposium on
Conference_Location
Albuquerque, NM
Print_ISBN
0-7803-5829-5
Type
conf
DOI
10.1109/FUSION.1999.849840
Filename
849840
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