Overview of impurity control and wall conditioning in NSTX

Kugel, H. W. ; Maingi, R. ; Wampler, W. ; Barry, R. E. ; Bell, M. ; Blanchard, W. ; Gates, D. ; Johnson, D. ; Kaita, R. ; Kaye, S. ; Maqueda, R. ; Menard, J. ; Menon, M. M. ; Mueller, D. ; Ono, M. ; Paul, S. ; Peng, Y-K. M. ; Raman, R. ; Roquemore, A. ; Skinner, C. H. ; Sabbagh, S. ; Stratton, B. ; Stutman, D. ; Wilson, J. R. ; Zweben, S. ; National Spherical Torus Experiment (Project)

Princeton University. Plasma Physics Laboratory.

关键词: Nstx Device;    70 Plasma Physics And Fusion Technology;    Deposition;    Control;    Plasma Impurities;   

DOI  :  10.2172/758243
RP-ID  :  PPPL-3469
RP-ID  :  AC02-76CH03073
RP-ID  :  758243

美国|英语

来源: UNT Digital Library

【 摘 要 】

The National Spherical Torus Experiment (NSTX) started plasma operations i n February 1999. In the first extended period of experiments, NSTX achieved high current, inner wall limited, double null, and single null plasma discharges, initial Coaxial Helicity Injection, and High Harmonic Fast Wave results. As expected, discharge reproducibility and performance were strongly affected by wall conditions. In this paper, the authors describe the internal geometry, and initial plasma discharge, impurity control, wall conditioning, erosion, and deposition results.