REVIEW OF THE NATIONAL SPHERICAL TORUS EXPERIMENT RESEARCH RESULTS.

Authors :: Mueller, D.
Menard, J. E.
Bell, M. G.
Bell, R. E.
Bialek, J. M.
Boedo, J. A.
Bush, C. E.
Crocker, N. A.
Diem, S.
Domier, C. W.
D’Ippolito, D. A.
Ferron, J. R.
Fredrickson, E. D.
Gates, D. A.
Hill, K. W.
Hosea, J. C.
Kaye, S. M.
Kessel, C. E.
Kubota, S.
Kugel, H. W.
Source :: AIP Conference Proceedings; 7/26/2009, Vol. 1154 Issue 1, p11-27, 17p, 17 Graphs
Publication Year :: 2009
Abstract: The National Spherical Torus Experiment (NSTX) produces plasmas, with toroidal aspect ratio as low as 1.25 and plasma currents up to 1.5 MA, which can be heated by up to 6 MW High-Harmonic Fast Waves and up to 7 MW of deuterium Neutral Beam Injection. With these capabilities, NSTX has already made considerable progress in advancing the scientific understanding of high performance plasmas needed for low-aspect-ratio reactor concepts and for ITER. In transport and turbulence research on NSTX, the role of magnetic shear is being elucidated in discharges in which electron energy transport barriers are observed. Scaling studies indicate a weaker dependence on plasma current than at conventional aspect ratio and a significant dependence on toroidal field (B<subscript>T</subscript>). [ABSTRACT FROM AUTHOR]