Overview of impurity control and wall conditioning in NSTX

Conference · Tue May 23 00:00:00 EDT 2000

OSTI ID:755685

Kugel, H W; Maingi, R; Wampler, W; Berry, R E

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 condition. 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: 755685
• Report Number(s): Cfpaper-4188; TRN: US0003778
• Resource Relation: Conference: 14 International Conference on Plasma Surface Interaction in Controlled Fusion Devices, Rosenheim (DE), 05/26/2000--05/30/2000; Other Information: PBD: 23 May 2000
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
NSTX DEVICE
PLASMA IMPURITIES
EROSION
DEPOSITION
FIRST WALL
OPERATION