Orbit following Monte Carlo code (ASCOT) calculations of neutral beam (NB) induced torque, current and heating have been performed for a selected set of plasma scenarios to optimise the neutral beam injection system for the proposed high magnetic field spherical tokamak ST40. It is found that there are strong variations especially in the current drive efficiency and in the toroidal torque depending on the NB alignment and injection energy. The optimal alignments as well as the optimal injection energy depend both on the scenario and whether the current drive or the toroidal torque is to be maximised. Due to the relatively small calculated current drive efficiency (0.05–0.2 MA/MW) we find that for the studied scenarios a relatively central l...
The SSPX spheromak experiment has achieved electron temperatures of 350eV and confinement consistent...
The Divertor Tokamak Test (DTT) is a new, super-conducting device, being constructed in Frascati, It...
The main purpose of the Divertor Tokamak Test (DTT) facility is to study alternative solutions to mi...
Orbit following Monte Carlo code (ASCOT) calculations of neutral beam (NB) induced torque, current a...
The capability of off-axis neutral beam heating and current drive has been investigated with NUBEAM ...
Recent theoretical studies on the use of neutral beams (NB), rotating magnetic fields (RMF) and heli...
The ST40 tokamak [1], built and operated by Tokamak Energy, has recently been upgraded with upper an...
Neutral beam injection heating is the most technically advanced and experimentally proven form of au...
Modification of the two existing DIII-D neutral beamlines is planned to allow vertical steering to p...
Three non inductive current drive methods that can be applied to compact toroids are studied. The us...
Thailand Institute of Nuclear Technology (TINT) is developing Thailand- 1 (TT-1) from a former devic...
Neutral beam injection (NBI) is one of the auxiliary power systems considered for the EU DEMO pulsed...
Toroidal rotation of plasmas in present-day tokamaks is beneficial for increasing the stability to w...
Neutral beam injection is a very robust tool for heating of high temperature plasmas and is used in ...
FNS-ST is a fusion neutron source project based on a spherical tokamak (R/a = 0.5 m/0.3 m) with a st...
The SSPX spheromak experiment has achieved electron temperatures of 350eV and confinement consistent...
The Divertor Tokamak Test (DTT) is a new, super-conducting device, being constructed in Frascati, It...
The main purpose of the Divertor Tokamak Test (DTT) facility is to study alternative solutions to mi...
Orbit following Monte Carlo code (ASCOT) calculations of neutral beam (NB) induced torque, current a...
The capability of off-axis neutral beam heating and current drive has been investigated with NUBEAM ...
Recent theoretical studies on the use of neutral beams (NB), rotating magnetic fields (RMF) and heli...
The ST40 tokamak [1], built and operated by Tokamak Energy, has recently been upgraded with upper an...
Neutral beam injection heating is the most technically advanced and experimentally proven form of au...
Modification of the two existing DIII-D neutral beamlines is planned to allow vertical steering to p...
Three non inductive current drive methods that can be applied to compact toroids are studied. The us...
Thailand Institute of Nuclear Technology (TINT) is developing Thailand- 1 (TT-1) from a former devic...
Neutral beam injection (NBI) is one of the auxiliary power systems considered for the EU DEMO pulsed...
Toroidal rotation of plasmas in present-day tokamaks is beneficial for increasing the stability to w...
Neutral beam injection is a very robust tool for heating of high temperature plasmas and is used in ...
FNS-ST is a fusion neutron source project based on a spherical tokamak (R/a = 0.5 m/0.3 m) with a st...
The SSPX spheromak experiment has achieved electron temperatures of 350eV and confinement consistent...
The Divertor Tokamak Test (DTT) is a new, super-conducting device, being constructed in Frascati, It...
The main purpose of the Divertor Tokamak Test (DTT) facility is to study alternative solutions to mi...