Title :
Performance of the C-Mod shape control system
Author :
Horne, S. ; Greenwald, M. ; Hutchinson, I. ; Wolfe, S. ; Tinios, G. ; Fredian, T. ; Stillerman, J.
Author_Institution :
Plasma Fusion Center, MIT, Cambridge, MA, USA
Abstract :
The poloidal field system for Alcator C-Mod (a high-field compact tokamak) can generate elongated, single or double null diverted plasmas. The shape control system consists of hardware (hybrid multiplier, real-time control computer, and associated electronics), the user interface (a set of X-Windows applications), and the underlying algorithms used by the interface to calculate the control matrices. The shape control computer generates demands to the power supplies, based on programmed waveforms and feedback from the diagnostics. Beginning in April 1993 we have used the shape control computer to program and/or feed-back control coil currents, power supply voltages, magnetic field quantities and gas pressure during plasma breakdown, and to tailor the fields during the current ramp. Representative data from the 1993 run and an evaluation of the overall performance of the shape control computer will be presented
Keywords :
Tokamak devices; fusion reactor instrumentation; plasma diagnostics; Alcator C-Mod; C-Mod shape control system; X-Windows; associated electronics; control matrices; current ramp; diagnostics feedback; double diverted plasmas; elongated diverted plasmas; gas pressure; hardware; high-field compact tokamak; hybrid multiplier; magnetic field quantities; plasma breakdown; poloidal field system; power supply voltages; programmed waveforms; real-time control computer; single diverted plasmas; user interface; Breakdown voltage; Computer interfaces; Control systems; Hardware; Plasma applications; Plasma waves; Power supplies; Real time systems; Shape control; Tokamaks;
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
DOI :
10.1109/FUSION.1993.518323
