FNS-ST is a fusion neutron source project based on a spherical tokamak (R/a = 0.5 m/0.3 m) with a steady-state neutron generation of ~10$^{18}$ n/s. Neutral beam injection (NBI) is supposed to maintain steady-state operation, non-inductive current drive and neutron production in FNS-ST plasma. In a low aspect ratio device, the toroidal magnetic field shape is not optimal for fast ions confinement in plasma, and the toroidal effects are more pronounced compared to the conventional tokamak design (with R/a > 2.5). The neutral beam production and the tokamak plasma response to NBI were efficiently modeled by a specialized beam-plasma software package BTR-BTOR, which allowed fast optimization of the neutral beam transport and evolution within t...
High power neutral beams currently play an important role in heating, fuelling and diagnosing magnet...
DEMO(DEMOnstration Fusion Power Plant) is a proposed nuclear fusion power plant that is intended to ...
The heating neutral beam injectors (HNBs) of ITER are designed to deliver 16.7MWof 1 MeVD0 or 0.87 ...
Neutral beam injection is supposed to be the main source of high-energy particles, driving non-induc...
Neutral beam injection (NBI) is one of the most used and reliable methods to heat plasmas in magneti...
We report measurements of the fusion reaction rate in the Tokamak Fusion Test Reactor (TFTR) coverin...
The fully non-inductive sustainment (Vloop~0) of high normalized beta (βN) plasmas is a crucial chal...
A tokamak neutron source that produces a neutron flux approximately 10$sup 13$ n/cm$sup 2$/s over a ...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
From topical meeting on technology of controlled nuclear fusion; San Diego, California, USA (16 Apr ...
For the FNS-ST compact neutron source, the dependence of the neutron yield on the tritium content in...
Neutral beam injection is a very robust tool for heating of high temperature plasmas and is used in ...
Neutral beam injection heating system is one of the main heating methods to improve the operating pa...
The neutral beam (NB) fast ion confinement in the Large Helical Device (LHD) is studied for several ...
Orbit following Monte Carlo code (ASCOT) calculations of neutral beam (NB) induced torque, current a...
High power neutral beams currently play an important role in heating, fuelling and diagnosing magnet...
DEMO(DEMOnstration Fusion Power Plant) is a proposed nuclear fusion power plant that is intended to ...
The heating neutral beam injectors (HNBs) of ITER are designed to deliver 16.7MWof 1 MeVD0 or 0.87 ...
Neutral beam injection is supposed to be the main source of high-energy particles, driving non-induc...
Neutral beam injection (NBI) is one of the most used and reliable methods to heat plasmas in magneti...
We report measurements of the fusion reaction rate in the Tokamak Fusion Test Reactor (TFTR) coverin...
The fully non-inductive sustainment (Vloop~0) of high normalized beta (βN) plasmas is a crucial chal...
A tokamak neutron source that produces a neutron flux approximately 10$sup 13$ n/cm$sup 2$/s over a ...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
From topical meeting on technology of controlled nuclear fusion; San Diego, California, USA (16 Apr ...
For the FNS-ST compact neutron source, the dependence of the neutron yield on the tritium content in...
Neutral beam injection is a very robust tool for heating of high temperature plasmas and is used in ...
Neutral beam injection heating system is one of the main heating methods to improve the operating pa...
The neutral beam (NB) fast ion confinement in the Large Helical Device (LHD) is studied for several ...
Orbit following Monte Carlo code (ASCOT) calculations of neutral beam (NB) induced torque, current a...
High power neutral beams currently play an important role in heating, fuelling and diagnosing magnet...
DEMO(DEMOnstration Fusion Power Plant) is a proposed nuclear fusion power plant that is intended to ...
The heating neutral beam injectors (HNBs) of ITER are designed to deliver 16.7MWof 1 MeVD0 or 0.87 ...