Thailand Institute of Nuclear Technology (TINT) is developing Thailand- 1 (TT-1) from a former device HT-6 M of China. The first hydrogen plasma will be initiated in 2023. To investigate high-β plasma and physics related to fast ions, TT-1 will be equipped with auxiliary heating systems. In this work, a feasibility study for installing a neutral beam injection (NBI) heating system in TT-1 is carried out. This work is motivated to characterize beam ion\u27s orbits in different injection angles and to explore a condition suitable in terms of higher heating efficiency. In this work, we assume that a hydrogen beam will be launched into the TT-1 plasma with an acceleration voltage of 20 kV. The orbit simulations using the gyromotion following co...
"The purpose of this paper is to review the present status of plasma heating in toroidal systems (ma...
The Divertor Tokamak Test (DTT) is a new, super-conducting device, being constructed in Frascati, It...
Thesis (Master's)--University of Washington, 2022Compared with more conventional toroidal magnetic c...
Thailand Tokamak-1 (TT-1) will be a small research tokamak being operated by the Thailand Institute ...
At the Lawrence Berkeley National Laboratory (LBNL) a diagnostic neutral beam injection system for ...
Abstract: This paper describes the configuration and commissioning of HL-1M neutral beam injection s...
The NCSX (National Compact Stellarator Experiment) has been designed to accommodate a variety of hea...
Neutral beam injection heating is the most technically advanced and experimentally proven form of au...
Plasma heating by injection of high energy neutrals is one of the experiments to be carried out on P...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
For heating of plasma in steady state superconducting tokamak (SST-1) tokamak [1-2] , a neutral beam...
Recent theoretical studies on the use of neutral beams (NB), rotating magnetic fields (RMF) and heli...
For the experimental fusion reactor ITER, which should show the feasibility of sustaining a fusion p...
The SSPX spheromak experiment has achieved electron temperatures of 350eV and confinement consistent...
For a fusion reaction to be feasible, it is necessary to heat plasmas to a very high temperature. On...
"The purpose of this paper is to review the present status of plasma heating in toroidal systems (ma...
The Divertor Tokamak Test (DTT) is a new, super-conducting device, being constructed in Frascati, It...
Thesis (Master's)--University of Washington, 2022Compared with more conventional toroidal magnetic c...
Thailand Tokamak-1 (TT-1) will be a small research tokamak being operated by the Thailand Institute ...
At the Lawrence Berkeley National Laboratory (LBNL) a diagnostic neutral beam injection system for ...
Abstract: This paper describes the configuration and commissioning of HL-1M neutral beam injection s...
The NCSX (National Compact Stellarator Experiment) has been designed to accommodate a variety of hea...
Neutral beam injection heating is the most technically advanced and experimentally proven form of au...
Plasma heating by injection of high energy neutrals is one of the experiments to be carried out on P...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
For heating of plasma in steady state superconducting tokamak (SST-1) tokamak [1-2] , a neutral beam...
Recent theoretical studies on the use of neutral beams (NB), rotating magnetic fields (RMF) and heli...
For the experimental fusion reactor ITER, which should show the feasibility of sustaining a fusion p...
The SSPX spheromak experiment has achieved electron temperatures of 350eV and confinement consistent...
For a fusion reaction to be feasible, it is necessary to heat plasmas to a very high temperature. On...
"The purpose of this paper is to review the present status of plasma heating in toroidal systems (ma...
The Divertor Tokamak Test (DTT) is a new, super-conducting device, being constructed in Frascati, It...
Thesis (Master's)--University of Washington, 2022Compared with more conventional toroidal magnetic c...