Results 1 to 10 of about 3,538 (193)

Advances in boronization on NSTX-Upgrade

open access: yesNuclear Materials and Energy, 2017
Boronization has been effective in reducing plasma impurities and enabling access to higher density, higher confinement plasmas in many magnetic fusion devices. The National Spherical Torus eXperiment, NSTX, has recently undergone a major upgrade to NSTX-
Dang Cai
exaly   +3 more sources

Electron cyclotron heating in NSTX [PDF]

open access: yesAIP Conference Proceedings, 1997
Heating and current drive by electron cyclotron waves in high magnetic field tokamaks is commonly done by coupling power from the low-field side to the O-mode. However, for tokamaks with ωpe/ωce>1, such as the spherical tokamak NSTX, the O-mode is cutoff throughout most of the plasma.
Bers, A.   +3 more
core   +3 more sources

Effect of boronization on plasma-facing graphite surfaces and its correlation with the plasma behavior in NSTX-U

open access: yesNuclear Materials and Energy, 2018
Boronization is a Plasma Facing Component (PFC) conditioning technique widely used in tokamak machines. The National Spherical Torus Experiment-Upgrade (NSTX-U) applied this conditioning, using a plasma glow with a deuterated Trimethyl-boron (d-TMB) and ...
Brian LaBombard, Robert Kaita
exaly   +3 more sources

NSTX-U Control System Upgrades

open access: yesFusion Engineering and Design, 2014
AbstractThe National Spherical Tokamak Experiment (NSTX) is undergoing a wealth of upgrades (NSTX-U). These upgrades, especially including an elongated pulse length, require broad changes to the control system that has served NSTX well. A new fiber serial Front Panel Data Port input and output (I/O) stream will supersede the aging copper parallel ...
Erickson, K.G.   +6 more
exaly   +2 more sources

Optimization of the snowflake divertor for power and particle exhaust on NSTX–U

open access: yesNuclear Materials and Energy, 2019
In this paper, simple analytical modeling and numerical simulations performed with the multi-fluid edge transport code UEDGE are used to identify optimal snowflake divertor (SFD) configurations for heat flux mitigation and sufficient cryopumping ...
Egemen Kolemen
exaly   +3 more sources

Elimination of inter-discharge helium glow discharge cleaning with lithium evaporation in NSTX [PDF]

open access: yesNuclear Materials and Energy, 2017
Operation in the National Spherical Torus Experiment (NSTX) typically used either periodic boronization and inter-shot helium glow discharge cleaning (HeGDC), or inter-shot lithium evaporation without boronization, and initially with inter-shot HeGDC. To
R. Maingi   +3 more
doaj   +2 more sources

Emission in the ion cyclotron range of frequencies (ICE) on NSTX and NSTX-U

open access: yesPhysics of Plasmas, 2019
We report here on observations of magnetic fluctuations in the ion-cyclotron frequency range on NSTX and NSTX-U. In many respects, the fluctuations appear similar to the ion cyclotron emission (ICE) seen in conventional tokamaks. However, a significant difference between previous observations of ICE and the ICE on NSTX is that the frequency of ICE in ...
Eric Fredrickson   +2 more
exaly   +3 more sources

Predictive modeling of a lithium vapor box divertor in NSTX-U using SOLPS-ITER

open access: yesNuclear Materials and Energy, 2021
The unmitigated heat flux in attached operation of a fusion power plant is predicted to be destructive to any solid divertor surface. Detachment, whereby the plasma pressure drops significantly before reaching the divertor target thus greatly reducing ...
Eric D Emdee   +2 more
exaly   +3 more sources

NSTX Tangential Divertor Camera [PDF]

open access: yesReview of Scientific Instruments, 2004
Strong magnetic field shear around the divertor x-point is numerically predicted to lead to strong spatial asymmetries in turbulence driven particle fluxes. To visualize the turbulence and associated impurity line emission near the lower x-point region, a new tangential observation port has been recently installed on NSTX.
Roquemore, A. L.   +5 more
openaire   +3 more sources

Diagnostic Development on NSTX [PDF]

open access: yes18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050), 1999
Diagnostics are described which are currently installed or under active development for the newly commissioned NSTX device. The low aspect ratio (R/a less than or equal to 1.3) and low toroidal field (0.1-0.3T) used in this device dictate adaptations in many standard diagnostic techniques.
Roquemore, A.L.   +3 more
openaire   +3 more sources

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