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
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;
Conference_Titel :
Fusion Engineering, 1999. 18th Symposium on
Conference_Location :
Albuquerque, NM
Print_ISBN :
0-7803-5829-5
DOI :
10.1109/FUSION.1999.849840
