Plasma 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 is used as input to a shape control algorithm known as isoflux control. The flux at the desired boundary location is compared to 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
Modifications to the plasma control capabilities and poloidal field coils of the National Spherical ...
MHD equilibrium and stability analyses have been performed in support of the design and initial expe...
In past years the Reversed Field Pinch RFX-mod has also been operated as a low current Tokamak to pe...
The implementation of the rtEFIT-isoflux algorithm in the digital control system for NSTX has led to...
The upgrade to the National Spherical Torus eXperiment (NSTX-U) included two main improvements: a la...
The NSTX is a national facility for the study of plasma confinement, heating, and current drive in a...
The National Spherical Torus Experiment (NSTX) has as one of its primary goals the demonstration of ...
The National Spherical Torus Experiment (NSTX) is a proof of scientific principle experiment as a ma...
The National Spherical Torus Experiment (NSTX) has explored the effects of shaping on plasma perform...
The National Spherical Torus Experiment (NSTX) has explored the effects of shaping on plasma perform...
This paper presents the development of a physics-based multiple-input-multiple-output algorithm for ...
In this paper, the authors describe recent work on plasma shape and position control at DIII-D. This...
The low aspect ratio and low magnetic field of the National Spherical Torus Experiment (NSTX) create...
The NSTX is a new national facility for the study of plasma confinement, heating, and current drive ...
A novel plasma position and shape controller has been developed for the highly flexible shaping polo...
Modifications to the plasma control capabilities and poloidal field coils of the National Spherical ...
MHD equilibrium and stability analyses have been performed in support of the design and initial expe...
In past years the Reversed Field Pinch RFX-mod has also been operated as a low current Tokamak to pe...
The implementation of the rtEFIT-isoflux algorithm in the digital control system for NSTX has led to...
The upgrade to the National Spherical Torus eXperiment (NSTX-U) included two main improvements: a la...
The NSTX is a national facility for the study of plasma confinement, heating, and current drive in a...
The National Spherical Torus Experiment (NSTX) has as one of its primary goals the demonstration of ...
The National Spherical Torus Experiment (NSTX) is a proof of scientific principle experiment as a ma...
The National Spherical Torus Experiment (NSTX) has explored the effects of shaping on plasma perform...
The National Spherical Torus Experiment (NSTX) has explored the effects of shaping on plasma perform...
This paper presents the development of a physics-based multiple-input-multiple-output algorithm for ...
In this paper, the authors describe recent work on plasma shape and position control at DIII-D. This...
The low aspect ratio and low magnetic field of the National Spherical Torus Experiment (NSTX) create...
The NSTX is a new national facility for the study of plasma confinement, heating, and current drive ...
A novel plasma position and shape controller has been developed for the highly flexible shaping polo...
Modifications to the plasma control capabilities and poloidal field coils of the National Spherical ...
MHD equilibrium and stability analyses have been performed in support of the design and initial expe...
In past years the Reversed Field Pinch RFX-mod has also been operated as a low current Tokamak to pe...