The implementation of the rtEFIT-isoflux algorithm in the digital control system for NSTX has led to improved ability to control the plasma shape. In particular, it has been essential for good gap control for radio-frequency experiments, for control of drsep in H-mode studies, and for X-point height control and {kappa} control in a variety of experiments
This paper presents the development of a physics-based multiple-input-multiple-output algorithm for ...
MHD equilibrium and stability analyses have been performed in support of the design and initial expe...
The major objective of the National Spherical Torus Experiment (NSTX) is to understand basic toroida...
Plasma shape control using real-time equilibrium reconstruction has been implemented on the National...
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 low aspect ratio and low magnetic field of the National Spherical Torus Experiment (NSTX) create...
The National Spherical Torus Experiment (NSTX) has explored the effects of shaping on plasma perform...
The National Spherical Torus Experiment (NSTX) is an innovative magnetic fusion device that was cons...
The National Spherical Torus Experiment (NSTX) has explored the effects of shaping on plasma perform...
The NSTX is a new national facility for the study of plasma confinement, heating, and current drive ...
The National Spherical Torus Experiment (NSTX) is a proof-of-principle experiment designed to study ...
Modifications to the plasma control capabilities and poloidal field coils of the National Spherical ...
This paper presents the development of a physics-based multiple-input-multiple-output algorithm for ...
MHD equilibrium and stability analyses have been performed in support of the design and initial expe...
The major objective of the National Spherical Torus Experiment (NSTX) is to understand basic toroida...
Plasma shape control using real-time equilibrium reconstruction has been implemented on the National...
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 low aspect ratio and low magnetic field of the National Spherical Torus Experiment (NSTX) create...
The National Spherical Torus Experiment (NSTX) has explored the effects of shaping on plasma perform...
The National Spherical Torus Experiment (NSTX) is an innovative magnetic fusion device that was cons...
The National Spherical Torus Experiment (NSTX) has explored the effects of shaping on plasma perform...
The NSTX is a new national facility for the study of plasma confinement, heating, and current drive ...
The National Spherical Torus Experiment (NSTX) is a proof-of-principle experiment designed to study ...
Modifications to the plasma control capabilities and poloidal field coils of the National Spherical ...
This paper presents the development of a physics-based multiple-input-multiple-output algorithm for ...
MHD equilibrium and stability analyses have been performed in support of the design and initial expe...
The major objective of the National Spherical Torus Experiment (NSTX) is to understand basic toroida...