PPPL-3827 is available in pdf format (1.9 MB).

Energetic Ion Behavior in the National Spherical Torus Experiment

Authors: S.S. Medley, R.E. Bell, E.D. Fredrickson, and A.L. Roquemore

Date of PPPL Report: June 2003

To be presented: at the 30th European Physical Society (EPS) Conference on Controlled Fusion and Plasma Physics in St. Petersburg, Russia, 7-11 July 2003.

The National Spherical Torus Experiment (NSTX) is a low aspect ratio (R/a approximately equal to 1.3) device with auxiliary heating from neutral beam injection (NBI) and high harmonic fast wave (HHFW) heating. Typical NSTX parameters are R0 = 85 cm, a = 67 cm, Ip less than or equal to 1.5 MA, BT = 0.3-0.6 T. Three co-directed deuterium neutral beam sources have injected PNB less than or equal to 6.2 MW at energies Eb less than or equal to 100 keV. HHFW heating has delivered up to PRF approximately equal to 6 MW to deuterium and helium plasmas.