Add to ORKGThe ASDEX Upgrade tokamak (R = 1.65m, a = 0.5m, κ 1:7) is equipped with a unique possibility for off-axis deposition of the Neutral Beam Injection (NBI). Two of the 8 beams (2.5 MW each) provide power deposition at about mid-radius of the vertical minor radius to drive off-axis current (NBCD) [1]. As presented in [2], the off-axis current drive is weake
The National Compact Stellarator Experiment (NCSX) will require 6 MW of 50 keV neutral beam injectio...
The fully non-inductive sustainment (Vloop~0) of high normalized beta (βN) plasmas is a crucial chal...
Two Neutral Beam Injectors (NBI) are foreseen to provide a substantial fraction of the heating power...
Modification of the two existing DIII-D neutral beamlines is planned to allow vertical steering to p...
Neutral beam injection is a very robust tool for heating of high temperature plasmas and is used in ...
The capability of off-axis neutral beam heating and current drive has been investigated with NUBEAM ...
Neutral beam current drive (NBCD) experiments in DIII-D using vertically shifted plasmas to move the...
Joint experiments investigating the off-axis neutral beam current drive (NBCD) capability to be util...
| openaire: EC/H2020/633053/EU//EUROfusionHeating and current drive systems such as high energy Neut...
Experiments have been carried out on the DIII-D tokamak to investigate whether off-axis NBI can: (a)...
Collective Thomson scattering (CTS) experiments have been carried out on ASDEX Upgrade (AUG) to stud...
The National Spherical Torus Experiment (NSTX) capability with a Neutral Beam Injector (NBI) capable...
Neutral beam injection (NBI) is an essential tool in tokamaks as a source of power, particle and tor...
Two of the eight neutral-beam sources on the DIII-D tokamak were modified to allow injection below t...
Here we report on efforts to improve performance and longevity of the Neutral Beam Injection (NBI) s...
The National Compact Stellarator Experiment (NCSX) will require 6 MW of 50 keV neutral beam injectio...
The fully non-inductive sustainment (Vloop~0) of high normalized beta (βN) plasmas is a crucial chal...
Two Neutral Beam Injectors (NBI) are foreseen to provide a substantial fraction of the heating power...
Modification of the two existing DIII-D neutral beamlines is planned to allow vertical steering to p...
Neutral beam injection is a very robust tool for heating of high temperature plasmas and is used in ...
The capability of off-axis neutral beam heating and current drive has been investigated with NUBEAM ...
Neutral beam current drive (NBCD) experiments in DIII-D using vertically shifted plasmas to move the...
Joint experiments investigating the off-axis neutral beam current drive (NBCD) capability to be util...
| openaire: EC/H2020/633053/EU//EUROfusionHeating and current drive systems such as high energy Neut...
Experiments have been carried out on the DIII-D tokamak to investigate whether off-axis NBI can: (a)...
Collective Thomson scattering (CTS) experiments have been carried out on ASDEX Upgrade (AUG) to stud...
The National Spherical Torus Experiment (NSTX) capability with a Neutral Beam Injector (NBI) capable...
Neutral beam injection (NBI) is an essential tool in tokamaks as a source of power, particle and tor...
Two of the eight neutral-beam sources on the DIII-D tokamak were modified to allow injection below t...
Here we report on efforts to improve performance and longevity of the Neutral Beam Injection (NBI) s...
The National Compact Stellarator Experiment (NCSX) will require 6 MW of 50 keV neutral beam injectio...
The fully non-inductive sustainment (Vloop~0) of high normalized beta (βN) plasmas is a crucial chal...
Two Neutral Beam Injectors (NBI) are foreseen to provide a substantial fraction of the heating power...