Neutral Beam Ion Confinement in NSTX

Darrow, D.S. ; Fredrickson, E.D. ; Kaye, S.M. ; Medley, S.S. ; Roquemore, and A.L.

Princeton University. Plasma Physics Laboratory.

关键词: Heating;    Magnetic Reconnection;    Nstx Device;    70 Plasma Physics And Fusion Technology;    Plasma Confinement;   

DOI  :  10.2172/787786
RP-ID  :  PPPL-3593
RP-ID  :  AC02-76CH03073
RP-ID  :  787786

美国|英语

来源: UNT Digital Library

【 摘 要 】

Neutral-beam (NB) heating in the National Spherical Torus Experiment (NSTX) began in September 2000 using up to 5 MW of 80 keV deuterium (D) beams. An initial assessment of beam ion confinement has been made using neutron detectors, a neutral particle analyzer (NPA), and a Faraday cup beam ion loss probe. Preliminary neutron results indicate that confinement may be roughly classical in quiescent discharges, but the probe measurements do not match a classical loss model. MHD activity, especially reconnection events (REs) causes substantial disturbance of the beam ion population.