Results 11 to 20 of about 1,608 (195)

ECRH/EBWH system for NSTX-U [PDF]

EPJ Web of Conferences, 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.
Hosea J.C., Harvey R.W., Ellis R.A., Taylor G., Smirnov A.P.   +4 more
doaj   +4 more sources

NSTX Electrical Power Systems [PDF]

18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050), 1999
The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physic Laboratory (PPPL). Most of the hardware, plant facilities, auxiliary sub-systems, and power systems originally used for the Tokamak Fusion Test Reactor (TFTR) have been used with suitable modifications to reflect NSTX ...
Ilic, A., Baker, E., Hatcher, R., Ramakrishnan, S., al, et   +4 more
core   +5 more sources

Overview of the NSTX Control System [PDF]

CoRR, 2001
The National Spherical Torus Experiment (NSTX) is an innovative magnetic fusion device that was constructed by the Princeton Plasma Physics Laboratory (PPPL) in collaboration with the Oak Ridge National Laboratory, Columbia University, and the University of Washington at Seattle. Since achieving first plasma in 1999, the device has been used for fusion
Sichta, P., Dong, J., Oliaro, G., Roney, P.   +3 more
core   +6 more sources

Making of the NSTX Facility [PDF]

, 1999
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 ...
Neumeyer, C., Ono, M., Kaye, S. M., Peng, Y. K. M., al, et   +4 more
openaire   +4 more sources

Kinetic Profiles in NSTX Plasmas [PDF]

, 2001
The National Spherical Torus Experiment (NSTX) is a low aspect ratio (R/a approximately 1.3) device with auxiliary heating from neutral-beam injection (NBI) and high-harmonic fast-wave heating (HHFW). Typical NSTX parameters are R(subscript ''0'') = 85 cm, a = 67 cm, I(subscript ''p'') = 0.7-1.4 MA, B(subscript ''phi'') = 0.25-0.45 T. Three co-directed
Bell, R. E., LeBlanc, B. P., Bourdelle, C., Ernst, D. R., Fredrickson, E. D., Gates, D. A., Hosea, J. C., Johnson, D. W., Kaye, S. M., Maingi, R., Medley, S., Menard, J. E., Mueller, D., Ono, M., Paoletti, F., Peng, M., Sabbagh, S. A., Stutman, D., Swain, D. W., Synakowski, E. J., Wilson, J. R.   +20 more
openaire   +4 more sources

NSTX/NSTX-U theory, modeling and analysis results

Nuclear Fusion, 2019
The mission of the spherical tokamak NSTX-U is to explore the physics that drives core and pedestal transport and stability at high-β and low collisionality, as part of the development of the spherical tokamak (ST) concept towards a compact, low-cost ST ...
S.M. Kaye, D.J. Battaglia, D. Baver, E. Belova, J.W. Berkery, V.N. Duarte, N. Ferraro, E. Fredrickson, N. Gorelenkov, W. Guttenfelder, G.Z. Hao, W. Heidbrink, O. Izacard, D. Kim, I. Krebs, R. La Haye, J. Lestz, D. Liu, L.A. Morton, J. Myra, D. Pfefferle, M. Podesta, Y. Ren, J. Riquezes, S.A. Sabbagh, M. Schneller, F. Scotti, V. Soukhanovskii, S.J. Zweben, J.W. Ahn, J.P. Allain, R. Barchfeld, F. Bedoya, R.E. Bell, N. Bertelli, A. Bhattacharjee, M.D. Boyer, D. Brennan, G. Canal, J. Canik, N. Crocker, D. Darrow, L. Delgado-Aparicio, A. Diallo, C. Domier, F. Ebrahimi, T. Evans, R. Fonck, H. Frerichs, K. Gan, S. Gerhardt, T. Gray, T. Jarboe, S. Jardin, M.A. Jaworski, R. Kaita, B. Koel, E. Kolemen, D.M. Kriete, S. Kubota, B.P. LeBlanc, F. Levinton, N. Luhmann, R. Lunsford, R. Maingi, R. Maqueda, J.E. Menard, D. Mueller, C.E. Myers, M. Ono, J.-K. Park, R. Perkins, F. Poli, R. Raman, M. Reinke, T. Rhodes, C. Rowley, D. Russell, E. Schuster, O. Schmitz, Y. Sechrest, C.H. Skinner, D.R. Smith, T. Stotzfus-Dueck, B. Stratton, G. Taylor, K. Tritz, W. Wang, Z. Wang, I. Waters, B. Wirth   +90 more
openaire   +3 more sources

Reversed magnetic shear scenario development in NSTX-U using TRANSP

Nuclear Fusion
Understanding and control of electron thermal transport is a critical point of research in magnetic fusion experiments. Previous experiments have shown that operation with reversed magnetic shear (RMS) can suppress electron thermal transport, resulting ...
M.E. Galante, M.D. Boyer, I.U. Uzun-Kaymak, E.L. Foley, B.P. LeBlanc, F.M. Levinton   +5 more
doaj   +2 more sources

Modeling of lithium granule injection in NSTX with M3D-C1 [PDF]

Nuclear Materials and Energy, 2017
In this paper we present initial simulations of pedestal control by Lithium Granule Injection (LGI) in NSTX. A model for small granule ablation has been implemented in the M3D-C1 code [1], allowing the simulation of realistic Lithium granule injections ...
A. Fil, E. Kolemen, A. Bortolon, N. Ferraro, S. Jardin, P.B. Parks, R. Lunsford, R. Maingi   +7 more
doaj   +2 more sources

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. A 1 MW 28 GHz gyrotron will be employed.
Taylor, G., Ellis, R. A., Harvey, R. W., Hosea, J. C., Smirnov, A. P.   +4 more
openaire   +3 more sources

Diagnostic Development for ST Plasmas on NSTX [PDF]

, 2003
Spherical tokamaks (STs) have much lower aspect ratio (a/R) and lower toroidal magnetic field, relative to tokamaks and stellarators. This paper will highlight some of the challenges and opportunities these features pose in the diagnosis of ST plasmas on
Team, NSTX, Johnson, D.
core   +1 more source