NDLI: Results of NSTX heating experiments

Content Provider	IEEE Xplore Digital Library
Author	Mueller, D. Ono, M. Bell, M.G. Bell, R.E. Bitter, M. Bourdelle, C. Darrow, D.S. Efthimion, P.C. Fredrickson, E.D. Gates, D.A. Goldston, R.J. Grisham, L.R. Hawryluk, R.J. Hill, K.W. Hosea, J.C. Jardin, S.C. Ji, H. Kaye, S.M. Kaita, R. Kugel, H.W. Johnson, D.W. LeBlanc, B.P. Majeski, R. Mazzucato, E. Medley, S.S. Menard, J.E. Park, H.K. Paul, S.F. Phillips, C.K. Redi, M.H. Rosenberg, A.L. Skinner, C.H. Soukhanovskii, V.A. Stratton, B. Synakowski, E.J. Taylor, G. Wilson, J.R. Zweben, S.J. Dorland, W.D. Peng, Y.K.M. Barry, R. Bigelow, T. Bush, C.E. Carter, M. Maingi, R. Menon, M. Ryan, P.M. Swain, D.W. Wilgen, J. Sabbagh, S.A. Paoletti, F. Bialek, J. Zhu, W. Raman, R. Jarboe, T.R. Nelson, B.A. Maqueda, R.J. Wurden, G.A. Pinsker, R.I. Schaffer, M. Ferron, J. Lao, L. Stutman, D. Finkenthal, M. Wampler, W. Kubota, S. Peebles, W.A. Gilmore, M. Mau, T.K. Lee, K.C. Domier, C.W. Deng, B.H. Johnson, M. Luhmann Jr., N.C. Bonoli, P. Bers, A. Ram, A. Akers, R. Takase, Y. Ejiri, A. Ono, Y. Shiraiwa, S. Nishino, N. Mitarai, O. Nagata, M. Yang, J.G. Na, H. Pacella, D.
Copyright Year	1973
Abstract	The National Spherical Torus Experiment (NSTX) at Princeton University, Princeton, NJ, 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 7 MW of neutral beam injection (NBI) at an injection energy of 100 keV and up to 6 MW of high harmonic fast wave (HHFW) at 30 MHz. NSTX has achieved /spl beta//sub T/ of 32%. A variety of MHD phenomena have been observed to limit /spl beta/. NSTX has now begun addressing /spl tau//sub E/ scaling, /spl beta/ limits, and current drive issues. During the NBI heating experiments, a broad T/sub i/ profile with T/sub i/ up to 2 keV, T/sub i/>T/sub e/ and a large toroidal rotation were observed. Transport analysis suggests that the impurity ions have diffusivities approaching neoclassical. For L-Mode plasmas, /spl tau//sub E/ is up to two times the ITER97L L-Mode scaling and exceeds the ITER98pby2 H-Mode scaling in some cases. Transitions to H-Mode have been observed which result in an approximate doubling of /spl tau//sub E/ after the transition in some conditions. During HHFW heating, T/sub e/>T/sub i/ and T/sub e/ up to 3.5 keV were observed. Current drive has been studied using both coaxial helicity injection with up to 390 kA of toroidal current and HHFW. HHFW has produced H-modes with significant bootstrap current fraction at low I/sub p/, high q, and high /spl beta//sub p/.
Sponsorship	IEEE Nuclear and Plasma Sciences Society
Starting Page	60
Ending Page	67
Page Count	8
File Size	574478
File Format	PDF
ISSN	00933813
Volume Number	31
Issue Number	1
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	2003-02-01
Publisher Place	U.S.A.
Access Restriction	One Nation One Subscription (ONOS)
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Heating Plasma confinement Magnetic confinement Toroidal magnetic fields Plasma waves Particle beams Particle beam injection Magnetohydrodynamics Impurities Plasma transport processes
Content Type	Text
Resource Type	Article
Subject	Nuclear and High Energy Physics Condensed Matter Physics

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