Neutral-beam (NB) heating in the National Spherical Torus Experiment (NSTX) began in September 2000 using up to 5 MW of 80 keV deuterium (D) beams. An initial assessment of beam ion confinement has been made using neutron detectors, a neutral particle analyzer (NPA), and a Faraday cup beam ion loss probe. Preliminary neutron results indicate that confinement may be roughly classical in quiescent discharges, but the probe measurements do not match a classical loss model. MHD activity, especially reconnection events (REs) causes substantial disturbance of the beam ion population
An increase of up to four-fold in the E||B Neutral Particle Analyzer (NPA) charge exchange neutral f...
A survey of the dependence of power balance on input power, shape, and plasma current was conducted ...
A numerical model, EIGOL, has been developed to calculate the loss rate of neutral beam ions from N...
The spherical torus (ST) concept underlies several contemporary plasma physics experiments, in which...
A range of effects may make fast ion confinement in spherical tokamaks worse than in conventional as...
Short ∼3 ms pulses of 80 keV deuterium neutrals are injected at three different tangency radii into ...
MHD-induced energetic ion loss in neutral-beam-heated H-mode [high-confinement mode] discharges in N...
Early neutral-beam injection is used in the National Spherical Torus Experiment (NSTX) to heat the e...
A scintillator based energetic ion loss detector has been built and installed on the National Spheri...
The prompt loss of neutral beam ions from the National Spherical Torus Experiment (NSTX) is expected...
The National Spherical Torus Experiment (NSTX) is a low aspect ratio (R/a approximately 1.3) device ...
The National Spherical Torus Experiment (NSTX) [1] is a midsize low aspect ratio fusion research fac...
The National Spherical Torus Experiment (NSTX) is a spherical tokamak with nominal plasma major radi...
The Neutral Particle Analyzer (NPA) diagnostic on the National Spherical Torus Experiment (NSTX) uti...
The National Spherical Torus Experiment (NSTX) at Princeton is designed to assess the potential of t...
An increase of up to four-fold in the E||B Neutral Particle Analyzer (NPA) charge exchange neutral f...
A survey of the dependence of power balance on input power, shape, and plasma current was conducted ...
A numerical model, EIGOL, has been developed to calculate the loss rate of neutral beam ions from N...
The spherical torus (ST) concept underlies several contemporary plasma physics experiments, in which...
A range of effects may make fast ion confinement in spherical tokamaks worse than in conventional as...
Short ∼3 ms pulses of 80 keV deuterium neutrals are injected at three different tangency radii into ...
MHD-induced energetic ion loss in neutral-beam-heated H-mode [high-confinement mode] discharges in N...
Early neutral-beam injection is used in the National Spherical Torus Experiment (NSTX) to heat the e...
A scintillator based energetic ion loss detector has been built and installed on the National Spheri...
The prompt loss of neutral beam ions from the National Spherical Torus Experiment (NSTX) is expected...
The National Spherical Torus Experiment (NSTX) is a low aspect ratio (R/a approximately 1.3) device ...
The National Spherical Torus Experiment (NSTX) [1] is a midsize low aspect ratio fusion research fac...
The National Spherical Torus Experiment (NSTX) is a spherical tokamak with nominal plasma major radi...
The Neutral Particle Analyzer (NPA) diagnostic on the National Spherical Torus Experiment (NSTX) uti...
The National Spherical Torus Experiment (NSTX) at Princeton is designed to assess the potential of t...
An increase of up to four-fold in the E||B Neutral Particle Analyzer (NPA) charge exchange neutral f...
A survey of the dependence of power balance on input power, shape, and plasma current was conducted ...
A numerical model, EIGOL, has been developed to calculate the loss rate of neutral beam ions from N...