Results 41 to 50 of about 1,399,245 (94)

ECRH/EBWH SYSTEM FOR NSTX-

, 2012
The National Spherical Torus Experiment Upgrade (NSTX-U) will operate at an axial toroidal field of up to 1 T, about twice the field available on NSTX. A 28 GHz electron cylotron resonance heating (ECRH) system is currently being planned for NSTX-U.
Taylor, G., Ellis, R. A., Harvey, R. W., Smirnov, A. P., Hosea, J. C.   +4 more
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Analysis Efforts Supporting NSTX Upgrades

, 2010
The National Spherical Torus Experiment (NSTX) is a low aspect ratio, spherical torus (ST) configuration device which is located at Princeton Plasma Physics Laboratory (PPPL) This device is presently being updated to enhance its physics by doubling the ...
H.Zhang, P. Titus, P. Rogoff, A.Zolfaghari, D. Mangra, M. Smith
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RF heating and current drive on NSTX with high harmonic fast waves [PDF]

, 2003
NSTX is a small aspect ratio tokamak (R = 0.85 m, a = 0.65 m). The High Harmonic Fast Wave (HHFW) system is a 30 MHz, 12-element array capable of launching both symmetric and directional wave spectra for plasma heating and non-inductive current drive. It
Mau, T., Mueller, D., Swain, D., Bell, R., Menard, J., Rasmussen, D., Wilgen, J., Wilson, J., Carter, M., Bernabei, S., Peng, Y., Pinsker, R., Kaye, S., Darrow, D., Gates, D., Phillips, C., Brambilla, M., Maingi, R., Medley, S., LeBlanc, B., Synakowski, E., Batchelor, D., Bonoli, P., Bell, M., Sabbagh, S., Cardinali, A., Hosea, J., Frederickson, E., Paoletti, F., Rosenberg, A., Jaeger, E., Ono, M., Bitter, J., Ryan, P.   +33 more
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Modeling of plasma rotation control for NSTX and NSTX-U

, 2016
This thesis studies some applications of feedback control design for plasma physics, specifically plasma drift waves and plasma toroidal rotation and covers two major steps: reduced-order modeling and controller design. This dissertation focuses
Goumiri, Imene
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Heating and current drive on NSTX and HHFW experiments on CDX-U [PDF]

, 1998
The NSTX (National Spherical Torus Experiment) device to be built at Princeton is a low-aspect-ratio toroidal device that has the achievement of high toroidal beta ({approximately} 45%) and noninductive operation as two of its main research goals.
Hosea, J., Grisham, L., Wilson, J. R.
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ECH on NSTX [PDF]

, 1997
Electron Cyclotron Heating has been proposed for plasma initiation, startup assistance and non-inductive startup on NSTX. One physics goal of NSTX will be to establish entirely non-inductive plasma operation by utilizing ECH to provide a sufficient start-
Carter, M. D., Batchelor, D. B., Bigelow, T. S., Peng, M., Wilson, J. R.   +4 more
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Innovative approaches towards an economic fusion reactor. [PDF]

Natl Sci Rev, 2020
Guo H, Thio FYC, Binderbauer MW, Buttery RJ, Jarboe TR, Maingi R, Sarff JS, Stangeby PC, Sutherland DA, Wade MR, Zarnstorff MC.   +10 more
europepmc   +1 more source

Spectroscopic characterization of composite lithium materials irradiated with high-temperature plasma. [PDF]

Heliyon, 2020
Budaev VP, Fedorovich SD, Lubenchenko AV, Karpov AV, Belova NE, Gubkin MK.   +5 more
europepmc   +1 more source

Compact steady-state tokamak performance dependence on magnet and core physics limits. [PDF]

Philos Trans A Math Phys Eng Sci, 2019
Menard JE.
europepmc   +1 more source

Edge Turbulence Velocity Changes with Lithium Coating on NSTX

, 2012
Lithium coating improves energy confinement and eliminates edge localized modes in NSTX, but the mechanism of this improvement is not yet well understood.
A. Cao, S.J. Zweben, D.P. Stotler, M. Bell, A. Diallo, S.M. Kaye and B. LeBlanc
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