Title :
Application of ITER CODAC Core System for NSTX SPA-2 project
Author :
Massry, A. ; Sichta, P. ; Dong, J.
Abstract :
The National Spherical Torus Experiment (NSTX) was upgraded in 2011 with a second switching power amplifier (SPA2) to power NSTX´s resistive wall mode (RWM) coils. Integration of the power supply´s local controls with the Central Instrumentation and Control System (CI&C) was accomplished, in part, through PLC-to-EPICS software that was included in the ITER project´s Control, Data Access, and Communication (CODAC) Core System. The Core System is a software suite for ITER plant system manufacturers to use as a template for development of their interface with CODAC. NSTX decided to use this software for the SPA2 project for a number of reasons, principally: 1) it was cost-effective for NSTX, 2) it provided an opportunity to collaborate with ITER and evaluate their Plant System Interface methodologies, documentation, and information technology and control system processes; on an operational machine. This paper will present an overview of the SPA2 CI&C interface and describe our experience using the ITER Core System software and applicable plant system integration processes.
Keywords :
Tokamak devices; fusion reactor instrumentation; fusion reactor operation; nuclear engineering computing; plasma toroidal confinement; Central Instrumentation and Control System; ITER CODAC Core System; ITER Core System software; ITER plant system; ITER project; NSTX RWM coils; NSTX SPA-2 project; National Spherical Torus Experiment; PLC-to-EPICS software; operational machine; plant system interface; power supply local controls; resistive wall mode; switching power amplifier; system integration processes; Control design; Magnetic cores; Servers; Software; Switches; World Wide Web;
Conference_Titel :
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location :
Chicago, IL
Print_ISBN :
978-1-4577-0669-1
Electronic_ISBN :
1078-8891
DOI :
10.1109/SOFE.2011.6052345