Published May 23, 2000
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Overview of impurity control and wall conditioning in NSTX
Description
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
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00755685; PURL: https://www.osti.gov/servlets/purl/755685-1uvUKq/webviewable/Files
31049305.pdf
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- Cfpaper--4188
Conference
- Title
- 14. International Conference on Plasma Surface Interactions in Controlled Fusion Devices
- Dates
- 22-27 May 2000
- Place
- Rosenheim (Germany)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 31049305
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEPOSITION; EROSION; FIRST WALL; NSTX DEVICE; OPERATION; PLASMA IMPURITIES
- Descriptors DEC
- CLOSED PLASMA DEVICES; IMPURITIES; SPHEROMAK DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES
Optional Information
- Contract/Grant/Project number
- AC02-76CH03073
- Funding organization
- USDOE Office of Energy Research (ER) (United States)