D.A. Gates et al 2006 Nucl. Fusion 46 17 doi:10.1088/0029-5515/46/1/002
Plasma shape control on the National Spherical Torus Experiment (NSTX) using real-time equilibrium reconstruction
D.A. Gates1, J.R. Ferron2, M. Bell1, T. Gibney1, R. Johnson2, R.J. Marsala1, D. Mastrovito1, J.E. Menard1, D. Mueller1, B. Penaflor2, S.A. Sabbagh3 and T. Stevenson1
Show affiliationsPlasma shape control using real-time equilibrium reconstruction has been implemented on the National Spherical Torus Experiment (NSTX). The rtEFIT code originally developed for use on DIII-D was adapted for use on NSTX. The real-time equilibria provide calculations of the flux at points on the plasma boundary, which are used as input to a shape control algorithm known as isoflux control. The flux at the desired boundary location is compared with a reference flux value, and this flux error is used as the basic feedback quantity for the poloidal field coils on NSTX. The hardware that comprises the control system is described, as well as the software infrastructure. Examples of precise boundary control are also presented.
- PACS
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52.55.Fa Tokamaks, spherical tokamaks
52.40.Hf Plasma-material interactions; boundary layer effects
- Subjects
- Dates
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Issue 1 (January 2006)
Received 15 April 2005, accepted for publication 27 October 2005
Published 8 December 2005
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Plasma shape control on the National Spherical Torus Experiment (NSTX) using real-time equilibrium reconstruction
D.A. Gates et al 2006 Nucl. Fusion 46 17
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