Results 31 to 40 of about 670 (162)
Onset of High-Harmonic Fast Wave Propagation in Annulus Geometry [PDF]
EPJ Web of ConferencesPrevious experiments on NSTX have reported high-harmonic fast wave (HHFW) power losses in the scrape-off layer (SOL), with dependencies on the wave parallel wavenumber, plasma density, and magnetic field.
Baek Seung-Gyou +4 more
doaj +1 more source
Diagnostic options for radiative divertor feedback control on NSTX-U [PDF]
Review of Scientific Instruments, 2012 A radiative divertor technique is used in present tokamak experiments and planned for ITER to mitigate high heat loads on divertor plasma-facing components (PFCs) to prevent excessive material erosion and thermal damage. In NSTX, a large spherical tokamak with lithium-coated graphite PFCs and high divertor heat flux (qpeak ⩽ 15 MW/m2), radiative ...
Soukhanovskii, V A +4 more
openaire +2 more sources
On the validity of the guiding-center approximation in the presence of strong magnetic gradients
, 2017 The motion of a charged particle in a nonuniform straight magnetic field with a uniform magnetic-field gradient is solved exactly in terms of elliptic functions. The connection between this problem and the guiding-center approximation is discussed. It is
Brizard, Alain J.
core +1 more source
Magnetic equilibrium and transport modeling of divertors for solutions to exhaust problems in tokamaks [PDF]
, 2017 Problems of intense exhaust heat and particle fluxes incident on material surfaces are obstacles for magnetic confinement fusion in tokamaks. Advanced divertors offer magnetic solutions to the problems by (a) increasing the plasma-wetted area via flux ...
Chen, Zhongping
core +1 more source
Magnetohydrodynamic normal mode analysis of plasma with equilibrium pressure anisotropy
, 2014 In this work, we generalise linear magnetohydrodynamic (MHD) stability theory to include equilibrium pressure anisotropy in the fluid part of the analysis.
Fitzgerald, M., Hole, M. J., Qu, Z. S.
core +1 more source
, 2018 Plasma fluctuations in the scrape-off layer of the Alcator C-Mod tokamak in ohmic and high confinement modes have been analyzed using gas puff imaging data. In all cases investigated, the time series of emission from a single spatially-resolved view into
Garcia, O. E. +4 more
core +1 more source
Full-$f$ gyrokinetic simulation of turbulence in a helical open-field-line plasma
, 2018 Curvature-driven turbulence in a helical open-field-line plasma is investigated using electrostatic five-dimensional gyrokinetic continuum simulations in an all-bad-curvature helical-slab geometry.
Hakim, Ammar +3 more
core +1 more source
NSTX-U Digital Coil Protection System software design
2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013 The National Spherical Torus Experiment (NSTX) currently uses a collection of analog signal processing solutions for coil protection. Part of the NSTX Upgrade (NSTX-U) entails replacing these analog systems with a software solution running on a conventional computing platform.
Keith G. Erickson +3 more
openaire +2 more sources
Studies of lithiumization and boronization of ATJ graphite PFCs in NSTX-U
Nuclear 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
Analysis of Tokamak fusion device parameters affecting the efficiency of Tokamak operation [PDF]
, 2017 Nuclear Power has been available as a relatively clean and reliable energy source for several decades. While tokamak engines have been in existence almost as long as successful fission-powered nuclear generators, they have not yet reached operational ...
Boyd-Weetman, Brendan +3 more
core +2 more sources