Zobrazeno 1 - 10
of 15
pro vyhledávání: '"NSTX Research Team"'
Autor:
M.G Bell, R.E Bell, D.A Gates, S.M Kaye, H Kugel, B.P LeBlanc, F.M Levinton, R Maingi, J.E Menard, R Raman, S.A Sabbagh, D Stutman, the NSTX Research Team
Publikováno v:
Nuclear Fusion. 46:S565-S572
The National Spherical Torus Experiment (NSTX) produces plasmas with toroidal aspect ratio as low as 1.25, which can be heated by up to 6 MW high-harmonic fast waves and up to 7 MW of deuterium neutral beam injection. Using new poloidal field coils,
Autor:
C.E Kessel, E.J Synakowski, M.E Bell, D.A Gates, R.W Harvey, S.M Kaye, T.K Mau, J Menard, C.K Phillips, G Taylor, R Wilson, the NSTX Research Team
Publikováno v:
Nuclear Fusion. 45:814-824
Integrated scenario simulations are done for NSTX that address four primary objectives for developing advanced spherical torus (ST) configurations: high ? and high ?N inductive discharges to study all aspects of ST physics in the high ? regime; non-i
Autor:
J.E Menard, R.E Bell, E.D Fredrickson, D.A Gates, S.M Kaye, B.P LeBlanc, R Maingi, S.S Medley, W Park, S.A Sabbagh, A Sontag, D Stutman, K Tritz, W Zhu, the NSTX Research Team
Publikováno v:
Nuclear Fusion. 45:539-556
Saturated internal kink modes have been observed in many of the highest toroidal β discharges of the National Spherical Torus Experiment (NSTX). These modes often cause rotation flattening in the plasma core, can degrade fast-ion confinement and in
Autor:
S.A Sabbagh, J.M Bialek, R.E Bell, A.H Glasser, B.P LeBlanc, J.E Menard, F Paoletti, M.G Bell, R Fitzpatrick, E.D Fredrickson, A.M Garofalo, D.A Gates, S.M Kaye, L.L Lao, R Maingi, D Mueller, G.A Navratil, D Stutman, W Zhu, the NSTX Research Team
Publikováno v:
Nuclear Fusion. 44:560-570
One of the goals of the National Spherical Torus Experiment (NSTX) is to investigate the physics of global mode stabilization in a low aspect ratio device. NSTX has a major radius R0 = 0.86 m, a midplane half-width of 0.7 m, and an on-axis vacuum tor
Autor:
B.P LeBlanc, R.E Bell, S.M Kaye, D Stutman, M.G Bell, M.L Bitter, C Bourdelle, D.A Gates, R Maingi, S.S Medley, J.E Menard, D Mueller, S.F Paul, A.L Roquemore, A Rosenberg, S.A Sabbagh, V.A Soukhanovskii, E.J Synakowski, J.R Wilson, the NSTX Research Team
Publikováno v:
Nuclear Fusion. 44:513-523
The confinement of auxiliary heated national spherical torus experiment discharges is discussed. From a database analysis, it is found that the energy confinement time in NBI heated plasmas with either L- or H-modes edge is up to 2.5 times the values
Autor:
J.E Menard, M.G Bell, R.E Bell, E.D Fredrickson, D.A Gates, S.M Kaye, B.P LeBlanc, R Maingi, D Mueller, S.A Sabbagh, D Stutman, C.E Bush, D.W Johnson, R Kaita, H.W Kugel, R.J Maqueda, F Paoletti, S.F Paul, M Ono, Y.-K.M Peng, C.H Skinner, E.J Synakowski, the NSTX Research Team
Publikováno v:
Nuclear Fusion. 43:330-340
Global magnetohydrodynamic (MHD) stability limits in the National Spherical Torus Experiment (NSTX) have increased significantly recently due to a combination of device and operational improvements. First, more routine H-mode operation with broadened
Autor:
E J Synakowski, M G Bell, R E Bell, C E Bush, C Bourdelle, D Darrow, W Dorland, A Ejiri, E D Fredrickson, D A Gates, S M Kaye, S Kubota, H W Kugel, B P LeBlanc, R Maingi, R J Maqueda, J E Menard, D Mueller, A Rosenberg, S A Sabbagh, D Stutman, G Taylor, D W Johnson, R Kaita, M Ono, F Paoletti, W Peebles, Y-K M Peng, A L Roquemore, C H Skinner, V A Soukhanovskii, the NSTX Research Team
Publikováno v:
ResearcherID
Rapidly developing diagnostic, operational, and analysis capability is enabling the first detailed local physics studies to begin in high β plasmas of the National Spherical Torus Experiment (NSTX). These studies are motivated in part by the observa
Autor:
S.A Sabbagh, S.M Kaye, J Menard, F Paoletti, M Bell, R.E Bell, J.M Bialek, M Bitter, E.D Fredrickson, D.A Gates, A.H Glasser, H Kugel, L.L Lao, B.P LeBlanc, R Maingi, R.J Maqueda, E Mazzucato, D Mueller, M Ono, S.F Paul, M Peng, C.H Skinner, D Stutman, G.A Wurden, W Zhu, NSTX Research Team
Publikováno v:
Nuclear Fusion. 41:1601-1611
Research in NSTX has been conducted to establish spherical torus plasmas to be used for high ?, auxiliary heated experiments. This device has a major radius R0 = 0.86?m and a midplane halfwidth of 0.7?m. It has been operated with toroidal magnetic fi
Autor:
R. Raman, T.R. Jarboe, D. Mueller, M.J. Schaffer, R. Maqueda, B.A. Nelson, S.A. Sabbagh, M.G. Bell, R. Ewig, E.D. Fredrickson, D.A. Gates, J.C. Hosea, S.C. Jardin, H. Ji, R. Kaita, S.M. Kaye, H.W. Kugel, L.L. Lao, R. Maingi, J. Menard, M. Ono, D. Orvis, F. Paoletti, S.F. Paul, Y.-K.M. Peng, C.H. Skinner, J.B. Wilgen, S.J. Zweben, NSTX Research Team
Publikováno v:
Nuclear Fusion. 41:1081-1086
Coaxial helicity injection (CHI) on the National Spherical Torus Experiment (NSTX) has produced 240 kA of toroidal current without the use of the central solenoid. Values of the current multiplication ratio (CHI produced toroidal current/injector cur
Autor:
R Raman, T R Jarboe, D Mueller, M J Schaffer, R Maqueda, B A Nelson, S Sabbagh, M Bell, R Ewig, E Fredrickson, D Gates, J Hosea, H Ji, R Kaita, S M Kaye, H Kugel, R Maingi, J Menard, M Ono, D Orvis, F Paoletti, S Paul, M Peng, C H Skinner, J B Wilgen, S Zweben, the NSTX Research Team
Publikováno v:
Plasma Physics and Controlled Fusion. 43:305-312
Coaxial helicity injection has been investigated on the National Spherical Torus Experiment (NSTX). Initial experiments produced 130 kA of toroidal current without the use of the central solenoid. The corresponding injector current was 20 kA. Dischar