The NCSX (National Compact Stellarator Experiment) has been designed to accommodate a variety of heating systems, including ohmic heating, neutral-beam injection, and radio-frequency. Neutral beams will provide one of the primary heating methods for NCSX. In addition to plasma heating, beams are also expected to provide a means for external control over the level of toroidal plasma rotation velocity and its profile. The plan is to provide 3 MW of 50 keV balanced neutral-beam tangential injection with pulse lengths of 500 msec for initial experiments, and to be upgradeable to pulse lengths of 1.5 sec. Subsequent upgrades will add 3 MW of neutral-beam injection. This Chapter discusses the NCSX neutral-beam injection requirements and design is...
The National Spherical Torus Experiment (NSTX) at Princeton is designed to assess the potential of t...
Thailand Institute of Nuclear Technology (TINT) is developing Thailand- 1 (TT-1) from a former devic...
The study of high-harmonic fast-wave (HHFW) heating and current drive is being conducted on the Nati...
The National Compact Stellarator Experiment (NCSX) has been designed to accommodate a variety of hea...
The National Compact Stellarator Experiment (NCSX) will require 6 MW of 50 keV neutral beam injectio...
"Confinement of ripple-trapped energetic ions is studied in a low-aspect-ratio helical system using ...
The National Spherical Torus Experiment Upgrade (NSTX-U) will operate at axial toroidal fields of ≤ ...
The SSPX spheromak experiment has achieved electron temperatures of 350eV and confinement consistent...
The NSTX (National Spherical Torus Experiment) device to be built at Princeton is a low-aspect-ratio...
In the Sustained Spheromak Physics Experiment, (SSPX) ['Improved operation of the SSPX spheromak', R...
The NSTX is a new US facility for the study of plasma confinement, heating, and current drive in a l...
Neutral beam injection heating is the most technically advanced and experimentally proven form of au...
30 MHz high-harmonic fast wave (HHFW) heating and current drive are being developed to assist fully ...
A megawatt-level, 28 GHz electron heating system is being designed to support non-inductive (NI) pla...
TCV is a tokamak device capable of many different plasma shapes, equipped with a flexible Electron C...
The National Spherical Torus Experiment (NSTX) at Princeton is designed to assess the potential of t...
Thailand Institute of Nuclear Technology (TINT) is developing Thailand- 1 (TT-1) from a former devic...
The study of high-harmonic fast-wave (HHFW) heating and current drive is being conducted on the Nati...
The National Compact Stellarator Experiment (NCSX) has been designed to accommodate a variety of hea...
The National Compact Stellarator Experiment (NCSX) will require 6 MW of 50 keV neutral beam injectio...
"Confinement of ripple-trapped energetic ions is studied in a low-aspect-ratio helical system using ...
The National Spherical Torus Experiment Upgrade (NSTX-U) will operate at axial toroidal fields of ≤ ...
The SSPX spheromak experiment has achieved electron temperatures of 350eV and confinement consistent...
The NSTX (National Spherical Torus Experiment) device to be built at Princeton is a low-aspect-ratio...
In the Sustained Spheromak Physics Experiment, (SSPX) ['Improved operation of the SSPX spheromak', R...
The NSTX is a new US facility for the study of plasma confinement, heating, and current drive in a l...
Neutral beam injection heating is the most technically advanced and experimentally proven form of au...
30 MHz high-harmonic fast wave (HHFW) heating and current drive are being developed to assist fully ...
A megawatt-level, 28 GHz electron heating system is being designed to support non-inductive (NI) pla...
TCV is a tokamak device capable of many different plasma shapes, equipped with a flexible Electron C...
The National Spherical Torus Experiment (NSTX) at Princeton is designed to assess the potential of t...
Thailand Institute of Nuclear Technology (TINT) is developing Thailand- 1 (TT-1) from a former devic...
The study of high-harmonic fast-wave (HHFW) heating and current drive is being conducted on the Nati...