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Author Kaita, R. ♦ Efthimion, P. ♦ Hoffman, D. ♦ Jones, B. ♦ Kugel, H. ♦ Majeski, R. ♦ Munsat, T. ♦ Raftopoulos, S. ♦ Taylor, G. ♦ Timberlake, J.
Sponsorship (US)
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Publisher The American Physical Society
Language English
Subject Keyword PLASMA PHYSICS AND FUSION TECHNOLOGY ♦ BOLOMETERS ♦ FIRST WALL ♦ LITHIUM ♦ POWER DENSITY ♦ RESOLUTION ♦ RETENTION ♦ SPECTROMETERS ♦ THERMONUCLEAR REACTORS ♦ THOMSON SCATTERING ♦ TRITIUM
Abstract A flowing liquid lithium first wall or divertor target could virtually eliminate the concerns with power density and erosion, tritium retention, and cooling associated with solid walls in fusion reactors. To investigate the interaction of a spherical torus plasma with liquid lithium limiters, large area divertor targets, and walls, discharges will be established in the Current Drive Experiment-Upgrade (CDX-U) where the plasma--wall interactions are dominated by liquid lithium surfaces. Among the unique CDX-U lithium diagnostics is a multilayer mirror (MLM) array, which will monitor the 13.5 nm LiIII line for core lithium concentrations. Additional spectroscopic diagnostics include a grazing incidence extreme ultraviolet (XUV) spectrometer (STRS) and a filterscope system to monitor D{sub {alpha}} and various impurity lines local to the lithium limiter. Profile data will be obtained with a multichannel tangential bolometer and a multipoint Thomson scattering system configured to give enhanced edge resolution. Coupons on the inner wall of the CDX-U vacuum vessel will be used for surface analysis. A 10000 frame per second fast visible camera and an IR camera will also be available.
ISSN 00346748
Educational Use Research
Learning Resource Type Article
Publisher Date 2001-01-01
Publisher Place United States
Journal Review of Scientific Instruments
Volume Number 72
Issue Number 1


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