Electron cyclotron current start-up using a retarding electric field in the QUEST spherical tokamak
Nuclear FusionThe plasma current start-up experiment is conducted through electron cyclotron (EC) heating in the QUEST spherical tokamak. During the EC heating, the application of a toroidal electric field in the opposite direction to the plasma current effectively ...
T. Onchi +26 more
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FAIR-MAST: A fusion device data management system
SoftwareXWe are introducing FAIR-MAST, a data management system designed for historical diagnostic data from the Mega Ampere Spherical Tokamak (MAST) fusion experiments.
Samuel Jackson +7 more
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System modelling and identification of Mega-Amp Spherical Tokamak
, 2001 A dynamic system response model for plasma in Mega-Amp Spherical Tokamak (MAST) has been developed using RZIP. This is a linearized tokamak model. It assumes a constant plasma current distribution and axisymmetry. The plasma and conducting structures are
J Qin +3 more
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MAST and the impact of low aspect ration on tokamak physics
, 2015 Mega ampere spherical tokamak (MAST) and the impact of low aspect ratio on tokamak physics are discussed. MAST is characterized by strong toroidicity, strong shaping and self fields, low magnetic field, high beta, and large plasma flow.
Applegate, D +7 more
core +1 more source
Plasma self-driven current in tokamaks with magnetic islands
Nuclear FusionMagnetic island perturbations may cause a reduction in plasma self-driven current that is needed for tokamak operation. A novel effect on tokamak self-driven current revealed by global gyrokinetic simulations is due to magnetic-island-induced 3D electric
W.X. Wang +5 more
doaj +1 more source
Fully-relativistic electron Bernstein wave current drive simulations in the STEP spherical tokamak [PDF]
Electron Bernstein waves (EBWs) are theorised to efficiently drive current in spherical tokamak power plants, e.g. Spherical Tokamak for Energy Production (STEP).
Roddy Vann +5 more
core +1 more source
Thermal energy confinement time of spherical tokamak plasmas in PI3
Nuclear FusionThe Plasma Injector 3 (PI3) experiment at general fusion has been constructed to demonstrate the ability to form plasma targets suitable for compression in a Magnetized Target Fusion machine.
A. Tancetti +18 more
doaj +1 more source
SOLPS-ITER simulations to study the impact of aspect ratio on edge fueling neutrals in tokamaks
Nuclear Materials and EnergyIn this paper, we examine the role of the aspect ratio on the neutral penetration and poloidal distribution for fixed magnetic geometry and plasma profiles using SOLPS-ITER. We start from an H-mode discharge from MAST (Kirk et al., 2012), with its aspect
Yi-Cheng Chuang +3 more
doaj +1 more source
Neutronics analysis of spin-polarized fuel in spherical tokamaks
Nuclear FusionThe effect of spin-polarized deuterium–tritium fuel on the blanket, magnets, and surrounding structures is analyzed for a spherical tokamak fusion power plant.
Jin Whan Bae +7 more
doaj +1 more source
Plasma Current Start-up by ECW and Vertical Field in the TST-2 Spherical Tokamak
Plasma current start-up and ramp-up to 10kA have been demonstrated in the TST-2 spherical tokamak without the use of the central solenoid. Only the electron cyclotron wave (ECW) and the outer equilibrium field coils are used. The plasma current evolution
ZUSHI Hideki +35 more
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