Real time control system for the National Spherical Torus Experiment (NSTX)

The NSTX is a new national facility for the study of plasma confinement, heating, and current drive in a low aspect ratio, spherical torus (ST) configuration. The ST configuration is an alternate magnetic confinement concept which is characterized by high /spl beta/ (ratio plasma pressure to magnetic held pressure) and low toroidal field compared to conventional tokamaks, and could provide a pathway to the realization of a practical fusion power source. The NSTX depends on a real time, high speed, synchronous, and deterministic control system acting on a system of thyristor rectifier power supplies to 1) establish the initial magnetic field configuration; 2) initiate plasma within the vacuum vessel; 3) inductively drive plasma current; and 4) control plasma position and shape.

[1]  P. Sichta,et al.  Computing hardware for the PBX-M Plasma Control System , 1995, Proceedings of 16th International Symposium on Fusion Engineering.

[2]  D. Mueller,et al.  Upgrade for the NSTX control computer , 1999, 1999 IEEE Conference on Real-Time Computer Applications in Nuclear Particle and Plasma Physics. 11th IEEE NPSS Real Time Conference. Conference Record (Cat. No.99EX295).

[3]  P. Heitzenroeder,et al.  Engineering overview of the National Spherical Torus Experiment (NSTX) , 1997, 17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131).