Overview of impurity control and wall conditioning in NSTX

Journal Article · Mon Jan 01 00:00:00 EST 2001 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/S0022-3115(00)00496-7· OSTI ID:1081850

Kugel, H. ^[1]; Peng, Yueng Kay Martin ^[2]

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1. Princeton Plasma Physics Laboratory (PPPL)
2. ORNL

The national spherical torus experiment (NSTX) started plasma operations in 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, we describe the internal geometry, and initial plasma discharge, impurity control, wail conditioning, erosion, and deposition results. (C) 2001 Elsevier Science B.V. All rights reserved.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1081850
• Journal Information: Journal of Nuclear Materials, Vol. 290-293; ISSN 0022-3115
• Country of Publication: United States
• Language: English