Results 61 to 70 of about 1,608 (195)

Physics Results from the National Spherical Torus Experiment [PDF]

, 2004
The National Spherical Torus Experiment (NSTX) produces plasmas with aspect ratio A {triple_bond} R/a = 0.85m/0.68m {approx} 1.25, at plasma currents up to 1.5 MA with vacuum toroidal magnetic field up to 0.6 T on axis.
Team, M.G. Bell for the NSTX Research
core   +1 more source

Sensitivity of WallDYN material migration modeling to uncertainties in mixed-material surface binding energies

Nuclear Materials and Energy, 2017
The WallDYN package has recently been applied to a number of tokamaks to self-consistently model the evolution of mixed-material plasma facing surfaces.
J.H. Nichols, M.A. Jaworski, K. Schmid
doaj   +1 more source

Conceptual design for the NSTX Central Instrumentation and Control System [PDF]

, 1997
The design and construction phase for the National Spherical Torus Experiment (NSTX) is under way at the Princeton Plasma Physics Laboratory (PPPL). Operation is scheduled to begin on April 30, 1999.
Sichta, P., Oliaro, G., Roney, P., Tindall, K., Bashore, D.   +4 more
core  

Importance of on ETG stability, turbulence, and transport in NSTX

Nuclear Fusion
This study employs electron-scale gyrokinetic simulations to investigate the electron temperature gradient (ETG) driven instabilities, turbulence, and transport in the pedestal region of the National Spherical Torus Experiment, comparing non-lithiated ...
P.-Y. Li, D.R. Hatch, J.F. Parisi, M. Lampert, E.A. Belli, M. Kotschenreuther, S.M. Mahajan   +6 more
doaj   +1 more source

Electron temperature gradient instability and transport analysis in NSTX and NSTX-U plasmas

Physics of Plasmas
Extensive linear and nonlinear simulations to study electron temperature gradient (ETG) stability and thermal transport in National Spherical Torus Experiment (NSTX) and NSTX-U plasmas were performed using the fully electromagnetic gyrokinetic code CGYRO.
C. F. Clauser, T. Rafiq, J. Parisi, G. Avdeeva, W. Guttenfelder, E. Schuster, C. Wilson   +6 more
openaire   +1 more source

Control System for the NSTX Lithium Pellet Injector [PDF]

, 2003
The Lithium Pellet Injector (LPI) is being developed for the National Spherical Torus Experiment (NSTX). The LPI will inject ''pellets'' of various composition into the plasma in order to study wall conditioning, edge impurity transport, liquid limiter ...
Sichta, P., Dong, J., Gettelfinger, G., Kugel, H., Gernhardt, R., null P. Sichta, null G. Gettelfinger, null R. Gernhardt, null H. Kugel, null J. Dong   +9 more
core   +1 more source

A plasma–material interaction design basis for NSTX-U flash lithium evaporators

Nuclear Materials and Energy
Plasma–material interaction (PMI) at lithium conditioned plasma facing components (PFCs) depends not only on lithium inventory, but also on coating freshness, chemical state, and spatial coverage.
A. Maan, R. Majeski, C. López Pérez, D.P. Boyle, T. Le, R. Lunsford   +5 more
doaj   +1 more source

Kinetic-ballooning-limited pedestals in spherical tokamak plasmas

Nuclear Fusion
A theoretical model is presented that for the first time matches experimental measurements of the pedestal width-height Diallo scaling in the low-aspect-ratio high- β tokamak NSTX.
J.F. Parisi, W. Guttenfelder, A.O. Nelson, R. Gaur, A. Kleiner, M. Lampert, G. Avdeeva, J.W. Berkery, C. Clauser, M. Curie, A. Diallo, W. Dorland, S.M. Kaye, J. McClenaghan, F.I. Parra   +14 more
doaj   +1 more source

Boronization on NSTX using Deuterated Trimethylboron [PDF]

, 2002
Boronization on the National Spherical Torus Experiment (NSTX) has proved to be quite beneficial with increases in confinement and density, and decreases in impurities observed in the plasma.
LaMarche, P.H., Blanchard, W.R., Kugel, H.W., Gernhardt, R.C.   +3 more
core   +1 more source

Current ramp-up studies for NSTX-U in support of the development of non-inductive current ramp-up scenarios in STs

Nuclear Fusion
The Spherical Tokamak (ST) is a low-aspect-ratio tokamak projected to enable simultaneous operation at high normalized toroidal beta and high bootstrap current fraction. However, a compact ST reactor cannot be built with a full-sized solenoid.
R. Raman, M. Ono, S.C. Jardin, J. Breslau, S.M. Kaye, M. Gorelenkova, T. Rafiq, A. Pankin   +7 more
doaj   +1 more source