Results 161 to 170 of about 3,538 (193)

Relativistic Effects in Electron Cyclotron Resonance Heating and Current Drive [PDF]

, 2008
Decker, Joan, Ram, Abhay
core  

Homeostatic plasticity at the Drosophila neuromuscular junction. [PDF]

Neuropharmacology, 2014
Frank CA.
europepmc   +1 more source

Current Drive by Electron Bernstein Waves in Spherical Tokamaks [PDF]

, 2004
Bers, A., Cairns, R.A., Davies, C.N., Decker, J., Efthimion, P.C., Peysson, Y., Ram, A.K., Taylor, G.   +7 more
core  

A control oriented strategy of disruption prediction to avoid the configuration collapse of tokamak reactors. [PDF]

Nat Commun
Murari A, Rossi R, Craciunescu T, Vega J, JET Contributors, Gelfusa M.   +5 more
europepmc   +1 more source

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ECH on NSTX

AIP Conference Proceedings, 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-up plasma to support further current drive from other heating systems. Scaling of previous ECH-only
Bigelow, T. S., Batchelor, D. B., Carter, M. D., Peng, M., Wilson, J. R.   +4 more
openaire   +1 more source

EUV spectroscopy on NSTX

Journal of Physics B: Atomic, Molecular and Optical Physics, 2010
Spectroscopy in the extreme ultraviolet region is important to magnetic fusion research as well as to astrophysics. We report on XEUS (X-ray and Extreme Ultraviolet Spectrometer) and LoWEUS (Long-Wavelength and Extreme Ultraviolet Spectrometer), which operate in the 5–400 A region on the NSTX (National Spherical Tokamak Experiment) tokamak.
J K Lepson, P Beiersdorfer, J Clementson, M F Gu, M Bitter, L Roquemore, R Kaita, P G Cox, A S Safronova   +8 more
openaire   +1 more source

Divertor regimes in NSTX

Journal of Nuclear Materials, 2005
Abstract The identification of divertor operating regimes is of particular importance for heat and particle control optimization in high performance plasmas of a spherical torus, because of the magnetic geometry effects and compactness of the divertor region.
V.A. Soukhanovskii, R. Maingi, A.L. Roquemore, J. Boedo, C. Bush, R. Kaita, H.W. Kugel, B.P. LeBlanc, S.F. Paul, G.D. Porter, N.S. Wolf   +10 more
openaire   +1 more source

Making of the NSTX facility

18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050), 2003
The NSTX (National Spherical Torus Experiment) facility located at Princeton Plasma Physics Laboratory is the newest national fusion science experimental facility for the restructured US Fusion Energy Science Program. The NSTX project was approved in FY 97 as the first proof-of-principle national fusion facility dedicated to the spherical torus ...
M. Ono, S.M. Kaye, C. Neumeyer, Y.-K.M. Peng, M. Williams, G. Barnes, M. Bell, J. Bialek, T. Bigelow, W. Blanchard, A. Brooks, M.D. Carter, J. Chrzanowski, W. Davis, L. Dudek, R. Ellis, H.M. Fan, E. Fredd, D. Gates, T. Gibney, P. Goranson, R.E. Hatcher, P. Heitzenroeder, J. Hosea, S.C. Jardin, T. Jarboe, D. Johnson, M. Kalish, R. Kaita, C. Kessel, H. Kugel, R. Majeski, B. McCormack, R. Maingi, J. Menard, R. Maqueda, R. Marsala, D. Mueller, B.E. Nelson, B.A. Nelson, G. Oliaro, F. Paoletti, R. Parsells, E. Perry, G. Pearson, S. Ramakrishnan, R. Raman, J. Robinson, P. Roney, L. Roquemore, P. Ryan, S. Sabbagh, P. Sichta, T. Stevenson, D. Swain, M. Viola, A. Von Halle, J.R. Wilson, G. Wurden, S. Zweben   +59 more
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NSTX upgrade power supply system

2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 2015
The National Spherical Torus Experiment (NSTX) is undergoing a significant upgrade. The upgrade increases the toroidal field and pulse length, adds three new diverter coils and a second neutral beam injection (NBI) system. The magnet coil power supply systems for the NSTX have been redesigned with many modifications to reflect NSTX upgrade needs.
W. Que, C. Neumeyer, S. Ramakrishnan, J. Lawson, R. Mozulay, X. Zhao, H. Schneider, K. Erickson   +7 more
openaire   +1 more source

NSTX high temperature sensor systems

18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050), 2003
The design of the more than 300 in-vessel sensor systems for the National Spherical Torus Experiment (NSTX) has encountered several challenging fusion reactor diagnostic issues involving high temperatures and space constraints. This has resulted in unique miniature, high temperature invessel sensor systems mounted in small spaces behind plasma facing ...
H.W. Kugel, B. McCormack, R. Kaita, P. Goranson, L. Gutttadora, R. Hatcher, T. Holoman, D. Johnson, B. Nelson, C. Neumeyer, A.L. Roquemore   +10 more
openaire   +1 more source