Zobrazeno 1 - 10
of 140
pro vyhledávání: '"E.J Synakowski"'
Autor:
E.J. Doyle (Chair Transport Physics), W.A. Houlberg (Chair Confinement Da Modelling), Y. Kamada (Chair Pedestal and Edge), V. Mukhovatov (co-Chair Transport Physics), T.H. Osborne (co-Chair Pedestal and Edge), A. Polevoi (co-Chair Confinement Da Modelling), G Bateman, J.W Connor, J.G. Cordey (retired), T Fujita, X Garbet, T.S Hahm, L.D Horton, A.E Hubbard, F Imbeaux, F Jenko, J.E Kinsey, Y Kishimoto, J Li, T.C Luce, Y Martin, M Ossipenko, V Parail, A Peeters, T.L Rhodes, J.E Rice, C.M Roach, V Rozhansky, F Ryter, G Saibene, R Sartori, A.C.C Sips, J.A Snipes, M Sugihara, E.J Synakowski, H Takenaga, T Takizuka, K Thomsen, M.R Wade, H.R Wilson, ITPA Transport Physics Topical Group, ITPA Confinement Database and Model Group, ITPA Pedestal and Edge Topical Group
Publikováno v:
Nuclear Fusion. 47:S18-S127
The understanding and predictive capability of transport physics and plasma confinement is reviewed from the perspective of achieving reactor-scale burning plasmas in the ITER tokamak, for both core and edge plasma regions. Very considerable progress
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:
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:
S.J Zweben, R.V Budny, D.S Darrow, S.S Medley, R Nazikian, B.C Stratton, E.J Synakowski, G. Taylor for the TFTR Group
Publikováno v:
Nuclear Fusion. 40:91-149
Alpha particle physics experiments were done on TFTR during its DT run from 1993 to 1997. These experiments utilized several new alpha particle diagnostics and hundreds of DT discharges to characterize the alpha particle confinement and wave-particle
Autor:
T. K. Mau, C.K. Phillips, G. Taylor, S.M. Kaye, R. Wilson, D.A. Gates, R.W. Harvey, C.E. Kessel, E.J. Synakowski, J. E. Menard
Integrated scenario simulations are done for NSTX [National Spherical Torus Experiment] that address four primary milestones for developing advanced ST configurations: high {beta} and high {beta}{sub N} inductive discharges to study all aspects of ST
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0f31ebe7a95cbe2eeac035aa8754cf91
https://doi.org/10.2172/836094
https://doi.org/10.2172/836094
Autor:
null D. Mueller, null M. Ono, null M.G. Bell, null R.E. Bell, null M. Bitter, null C. Bourdelle, null D.S. Darrow, null P.C. Efthimion, null E.D. Fredrickson, null D.A Gates, null R.J. Goldston, null L.R. Grisham, null R.J. Hawryluk, null K.W. Hill, null J.C. Hosea, null S.C. Jardin, null H. Ji, null S.M. Kaye, null R. Kaita, null H.W. Kugel, null D.W. Johnson, null B.P. LeBlanc, null R. Majeski, null E. Mazzucato, null S.S. Medley, null J.E. Menard, null H.K. Park, null S.F. Paul, null C.K. Phillips, null M.H. Redi, null A.L. Rosenberg, null C.H. Skinner, null V.A. Soukhanovskii, null B. Stratton, null E.J Synakowski, null G. Taylor, null J.R. Wilson, null S.J. Zweben, null Y-K.M. Peng, null R. Barry, null T. Bigelow, null C.E. Bush, null M. Carter, null R. Maingi, null M. Menon, null P.M. Ryan, null D.W. Swain, null J. Wilgen, null 37 additional authors
The National Spherical Torus Experiment (NSTX) at Princeton is designed to assess the potential of the low-aspect-ratio spherical torus concept for magnetic plasma confinement. The plasma has been heated by up to 5 MW of neutral beam injection, NBI,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9bfc18b375a24cb93d9f075df7699cd2
https://doi.org/10.2172/798203
https://doi.org/10.2172/798203
Autor:
null J.E. Menard, null R.E.Bell, null C. Bourdelle, null D.S. Darrow, null E.D. Fredrickson, null D.A. Gates, null L.R. Grisham, null S.M. Kaye, null B.P. LeBlanc, null R. Maingi, null S.S. Medley, null D. Mueller, null F. Paoletti, null S.A. Sabbagh, null D. Stutman, null D.W. Swain, null J.R. Wilson, null M.G. Bell, null J.M. Bialek, null C.E.Bush, null J.C. Hosea, null D.W. Johnson, null R. Kaita, null H.W. Kugel, null R.J. Maqueda, null M. Ono, null Y-K.M. Peng, null C.H. Skinner, null V.A. Soukhanovskii, null E.J. Synakowski, null G. Taylor, null G.A. Wurden, null and S.J. Zweben
The National Spherical Torus Experiment (NSTX) is a spherical tokamak with nominal plasma major radius R(subscript ''0'') = 0.85 m, minor radius a = 0.66 m, and aspect ratio A > 1.28. Typical discharge parameters are plasma current I (subscript ''p''
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::383362486c44945ee27cc1b7c419fc20
https://doi.org/10.2172/787717
https://doi.org/10.2172/787717