Results 71 to 80 of about 3,538 (193)

Self-consistent calculation of the effects of RF injection in the HHFW heating regimes on the evolution of fast ions in toroidal plasmas

open access: yesEPJ Web of Conferences, 2017
A critical question for the use of ion cyclotron range of frequency (ICRF) heating in the ITER device and beyond is interaction of fast waves with energetic ion populations from neutral beam injection (NBI), fusion reactions, and minority ions ...
Bertelli Nicola   +5 more
doaj   +1 more source

Studies of lithiumization and boronization of ATJ graphite PFCs in NSTX-U

open access: yesNuclear Materials and Energy, 2017
This work examines the effect of boron and lithium conditioned ATJ graphite surface bombarded by low-energy deuterium atoms on the deuterium retention and chemical sputtering.
F.J. Domínguez-Gutiérrez   +5 more
doaj   +1 more source

Real-time capable modeling of ICRF heating on NSTX and WEST via machine learning approaches

open access: yesNuclear Fusion
A real-time capable core Ion Cyclotron Range of Frequencies (ICRF) heating model on NSTX and WEST is developed. The model is based on two nonlinear regression algorithms, the random forest ensemble of decision trees and the multilayer perceptron neural ...
Á. Sánchez-Villar   +8 more
doaj   +1 more source

NSTX power supply real time controller [PDF]

open access: yes, 2000
The NSTX is a new national facility for the study of plasma confinement, heating, and current drive in a low aspect ratio, spherical torus (ST) configuration. The ST configuration is an alternate magnetic confinement concept which is characterized by high beta (ratio plasma pressure to magnetic field pressure) and low toroidal field compared to ...
Neumeyer, C.   +3 more
openaire   +2 more sources

Stability and transport of gyrokinetic critical pedestals

open access: yesNuclear Fusion
A gyrokinetic threshold model for pedestal width–height scaling prediction is applied to multiple devices. A shaping and aspect ratio scan is performed on National Spherical Torus Experiment (NSTX) equilibria, finding $\Delta_{\mathrm{ped}} = 0.92 A^{1 ...
J.F. Parisi   +13 more
doaj   +1 more source

Neutral Beam Ion Confinement in NSTX [PDF]

open access: yes, 2001
Neutral-beam (NB) heating in the National Spherical Torus Experiment (NSTX) began in September 2000 using up to 5 MW of 80 keV deuterium (D) beams. An initial assessment of beam ion confinement has been made using neutron detectors, a neutral particle analyzer (NPA), and a Faraday cup beam ion loss probe.
Darrow, D. S.   +4 more
openaire   +2 more sources

Nonlinear parallel momentum transport in strong turbulence

open access: yes, 2015
Most existing theoretical studies of momentum transport focus on calculating the Reynolds stress based on quasilinear theory, without considering the \emph{nonlinear} momentum flux-$$.
Diamond, P. H., Wang, Lu, Wen, Tiliang
core   +1 more source

Numerical assessment of the impact of the guiding-centre approximation on fast ion simulations in NSTX

open access: yesNuclear Fusion
Guiding-centre (GC) and full-orbit (FO) simulations of the beam-injected fast ion distribution and the corresponding neutron emissivity have been carried out for magnetohydrodynamics-quiescent National Spherical Torus eXperiment (NSTX) plasmas, using a ...
I. Dolby   +4 more
doaj   +1 more source

Fast Neutral Pressure Gauges in NSTX [PDF]

open access: yes, 2004
Successful operation in NSTX of two prototype fast-response micro ionization gauges during plasma operations has motivated us to install five gauges at different toroidal and poloidal locations to measure the edge neutral pressure and its dependence on the type of discharge (L-mode, H-mode, CHI) and the fueling method and location.
Raman, R.   +5 more
openaire   +2 more sources

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