Published May 23, 2000 | Version v1
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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/

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Additional details

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)