Overview of impurity control and wall conditioning in NSTX

Technical Report · Fri Jul 14 00:00:00 EDT 2000

DOI:https://doi.org/10.2172/758243· OSTI ID:758243

Kugel, H W ^[1]; 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

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1. Princeton Plasma Physics Laboratory

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.

• Research Organization: Princeton Plasma Physics Lab., NJ (US)
• Sponsoring Organization: USDOE Office of Energy Research (ER) (US)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 758243
• Report Number(s): PPPL-3469
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CONTROL
DEPOSITION
EROSION
NSTX DEVICE
OPERATION
PLASMA IMPURITIES
THERMONUCLEAR REACTOR WALLS