Energetic Ion Behavior in the National Spherical Torus Experiment

Medley, S.S. ; Bell, R.E. ; Fredrickson, E.D. ; Roquemore, A.L.

Princeton University. Plasma Physics Laboratory.

关键词: Beam Injection;    Heating;    Auxiliary Heating;    70 Plasma Physics And Fusion Technology;    Spherical Torus;   

DOI  :  10.2172/814691
RP-ID  :  PPPL-3827
RP-ID  :  AC02-76CH03073
RP-ID  :  814691

美国|英语

来源: UNT Digital Library

【 摘 要 】

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 R(sub)0 = 85 cm, a = 67 cm, I(sub)p less than or equal to 1.5 MA, B(sub)T = 0.3-0.6 T. Three co-directed deuterium neutral beam sources have injected P(sub)NB less than or equal to 6.2 MW at energies E(sub)b less than or equal to 100 keV. HHFW heating has delivered up to P(sub)RF approximately equal to 6 MW to deuterium and helium plasmas.