Results 101 to 110 of about 1,577 (223)
Current rearrangement in merging start-up of spherical tokamak plasmas
Torus plasma merging technique that provides high power ion heating by magnetic reconnection is expected to significantly expand the operation scenarios of spherical tokamak (ST) fusion reactors.
M. Inomoto +14 more
doaj +1 more source
Dynamics of spherical tokamak plasma on the internal reconnection event
Nonlinear magnetohydrodynamic (MHD) simulations are executed to investigate the dynamical behavior of the relaxation phenomenon observed in spherical tokamak (ST) plasma that is known as the Internal Reconnection Event (IRE).
Mizuguchi, Naoki +5 more
core +1 more source
The most relevant features of FLIPEC (Free fLow Iterative Plasma Equilibrium Code) are presented. This new code iteratively calculates free-boundary, axisymmetric ideal MHD equilibria with arbitrary poloidal and toroidal plasma flows.
G. F.-Torija Daza +4 more
doaj +1 more source
Neutral beam optimisation for the spherical tokamak ST40
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 ...
Salmi, Antti +9 more
core +1 more source
Nonlinear Simulations of Internal Reconnection Event in Spherical Tokamak
"Three dimensional magnetohydrodynamic simulations are executed in a full toroidal geometry to clarify the physical mechanisms of the Internal Reconnection Event (IRE), which is observed in the spherical tokamak experiments.
Mizuguchi, N. +4 more
core
FAIR-MAST: A fusion device data management system
We 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
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
Plasma self-driven current in tokamaks with magnetic islands
Magnetic 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
Thermal energy confinement time of spherical tokamak plasmas in PI3
The 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
In 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

