The National Spherical Torus Experiment (NSTX) capability with a Neutral Beam Injector (NBI) capable of 80 kiloelectronvolt (keV), 5 Megawatt (MW), 5 second operation. This 5.95 million dollar upgrade reused a previous generation injector and equipment for technical, cost, and schedule reasons to obtain these specifications while retaining a legacy capability of 120 keV neutral particle beam delivery for shorter pulse lengths for possible future NSTX experiments. Concerns with NBI injection included power deposition in the plasma, aiming angles from the fixed NBI fan array, density profiles and beam shine through, orbit losses of beam particles, and protection of the vacuum vessel wall against beam impingement. The upgrade made use of the b...
The National Compact Stellarator Experiment (NCSX) has been designed to accommodate a variety of hea...
The present ITER NB system includes two design features: short beamline design and vacuum insulated ...
Recent upgrades to the NSTX facility have led to improved plasma performance. Using 5MW of neutral b...
The National Compact Stellarator Experiment (NCSX) will require 6 MW of 50 keV neutral beam injectio...
The NSTX is a new US facility for the study of plasma confinement, heating, and current drive in a l...
The main aim of National Spherical Torus Experiment (NSTX) is to establish the fusion physics princi...
The ITER neutral beam (NB) injectors are the first injectors that will have to operate under conditi...
The NSTX is a new US facility for the study of plasma confinement, heating, and current drive in a l...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
The National Spherical Torus Experiment (NSTX) is currently being upgraded to operate at twice the t...
International audienceAchievement of an economic fusion reactor imposes a high level of unprecedente...
The National Spherical Torus Experiment (NSTX) is being built at PPPL to test the fusion physics pri...
The major objective of the National Spherical Torus Experiment (NSTX) is to understand basic toroida...
The National Spherical Torus Experiment (NSTX) is a low aspect ratio, spherical torus (ST) configura...
The National Spherical Torus Experiment (NSTX) is a low aspect ratio (R/a approximately 1.3) device ...
The National Compact Stellarator Experiment (NCSX) has been designed to accommodate a variety of hea...
The present ITER NB system includes two design features: short beamline design and vacuum insulated ...
Recent upgrades to the NSTX facility have led to improved plasma performance. Using 5MW of neutral b...
The National Compact Stellarator Experiment (NCSX) will require 6 MW of 50 keV neutral beam injectio...
The NSTX is a new US facility for the study of plasma confinement, heating, and current drive in a l...
The main aim of National Spherical Torus Experiment (NSTX) is to establish the fusion physics princi...
The ITER neutral beam (NB) injectors are the first injectors that will have to operate under conditi...
The NSTX is a new US facility for the study of plasma confinement, heating, and current drive in a l...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
The National Spherical Torus Experiment (NSTX) is currently being upgraded to operate at twice the t...
International audienceAchievement of an economic fusion reactor imposes a high level of unprecedente...
The National Spherical Torus Experiment (NSTX) is being built at PPPL to test the fusion physics pri...
The major objective of the National Spherical Torus Experiment (NSTX) is to understand basic toroida...
The National Spherical Torus Experiment (NSTX) is a low aspect ratio, spherical torus (ST) configura...
The National Spherical Torus Experiment (NSTX) is a low aspect ratio (R/a approximately 1.3) device ...
The National Compact Stellarator Experiment (NCSX) has been designed to accommodate a variety of hea...
The present ITER NB system includes two design features: short beamline design and vacuum insulated ...
Recent upgrades to the NSTX facility have led to improved plasma performance. Using 5MW of neutral b...