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Title: Diagnostics for liquid lithium experiments in CDX-U

Abstract

A flowing liquid lithium first wall or diverter 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 diverter 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 multi-layer mirror (MLM) array, which will monitor the 135 {angstrom} LiIII line for core lithium concentrations. Additional spectroscopic diagnostics include a grazing incidence 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 th e inner wall of the CDX-U vacuum vessel will be used for surface analysis. A 10,000 frame per second fast visible camera and an IR camera will also be available.

Authors:
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Publication Date:
Research Org.:
Princeton Plasma Physics Lab., NJ (US)
Sponsoring Org.:
USDOE Office of Energy Research (ER) (US)
OSTI Identifier:
756819
Report Number(s):
PPPL-3455
TRN: US0003690
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 21 Jun 2000
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; PLASMA DIAGNOSTICS; CDX-U SPHEROMAK; LIMITERS; LIQUID METALS; LITHIUM; ULTRAVIOLET SPECTROMETERS; PLASMA IMPURITIES; THOMSON SCATTERING; CAMERAS

Citation Formats

R. Kaita, P. Efthimion, D. Hoffman, B. Jones, H. Kugel, R. Majeski, T. Munsat, S. Raftopoulos, G. Taylor, J. Timberlake, V. Soukhanovskii, D. Stutman, M. Iovea, M. Finkenthal, R. Doerner, S. Luckhardt, R. Maingi, and R. Causey. Diagnostics for liquid lithium experiments in CDX-U. United States: N. p., 2000. Web. doi:10.2172/756819.
R. Kaita, P. Efthimion, D. Hoffman, B. Jones, H. Kugel, R. Majeski, T. Munsat, S. Raftopoulos, G. Taylor, J. Timberlake, V. Soukhanovskii, D. Stutman, M. Iovea, M. Finkenthal, R. Doerner, S. Luckhardt, R. Maingi, & R. Causey. Diagnostics for liquid lithium experiments in CDX-U. United States. doi:10.2172/756819.
R. Kaita, P. Efthimion, D. Hoffman, B. Jones, H. Kugel, R. Majeski, T. Munsat, S. Raftopoulos, G. Taylor, J. Timberlake, V. Soukhanovskii, D. Stutman, M. Iovea, M. Finkenthal, R. Doerner, S. Luckhardt, R. Maingi, and R. Causey. Wed . "Diagnostics for liquid lithium experiments in CDX-U". United States. doi:10.2172/756819. https://www.osti.gov/servlets/purl/756819.
@article{osti_756819,
title = {Diagnostics for liquid lithium experiments in CDX-U},
author = {R. Kaita and P. Efthimion and D. Hoffman and B. Jones and H. Kugel and R. Majeski and T. Munsat and S. Raftopoulos and G. Taylor and J. Timberlake and V. Soukhanovskii and D. Stutman and M. Iovea and M. Finkenthal and R. Doerner and S. Luckhardt and R. Maingi and R. Causey},
abstractNote = {A flowing liquid lithium first wall or diverter 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 diverter 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 multi-layer mirror (MLM) array, which will monitor the 135 {angstrom} LiIII line for core lithium concentrations. Additional spectroscopic diagnostics include a grazing incidence 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 th e inner wall of the CDX-U vacuum vessel will be used for surface analysis. A 10,000 frame per second fast visible camera and an IR camera will also be available.},
doi = {10.2172/756819},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2000},
month = {6}
}