학술논문
Results of NSTX heating experiments
Document Type
Periodical
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, N.C., Jr.; 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.
Source
IEEE Transactions on Plasma Science IEEE Trans. Plasma Sci. Plasma Science, IEEE Transactions on. 31(1):60-67 Feb, 2003
Subject
Language
ISSN
0093-3813
1939-9375
1939-9375
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/.