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Title: Effects of Large Area Liquid Lithium Limiters on Spherical Torus Plasmas

Abstract

Use of a large-area liquid lithium surface as a first wall has significantly improved the plasma performance in the Current Drive Experiment-Upgrade (CDX-U) at the Princeton Plasma Physics Laboratory. Previous CDX-U experiments with a partially-covered toroidal lithium limiter tray have shown a decrease in impurities and the recycling of hydrogenic species. Improvements in loading techniques have permitted nearly full coverage of the tray surface with liquid lithium. Under these conditions, there was a large drop in the loop voltage needed to sustain the plasma current. The data are consistent with simulations that indicate more stable plasmas having broader current profiles, higher temperatures, and lowered impurities with liquid lithium walls. As further evidence for reduced recycling with a liquid lithium limiter, the gas puffing had to be increased by up to a factor of eight for the same plasma density achieved with an empty toroidal tray limiter.

Authors:
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Publication Date:
Research Org.:
Princeton Plasma Physics Lab., Princeton, NJ (US)
Sponsoring Org.:
USDOE Office of Science (SC) (US)
OSTI Identifier:
828014
Report Number(s):
PPPL-3963
TRN: US0403831
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 7 Jun 2004
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ELECTRIC CURRENTS; FIRST WALL; IMPURITIES; LITHIUM; PERFORMANCE; PHYSICS; PLASMA; PLASMA DENSITY; RECYCLING; PLASMA-WALL INTERACTION; SPHERICAL TORUS

Citation Formats

R. Kaita, R. Majeski, M. Boaz, P. Efthimion, G. Gettelfinger, T. Gray, D. Hoffman, S. Jardin, H. Kugel, P. Marfuta, T. Munsat, C. Neumeyer, S. Raftopoulos, V. Soukhanovskii, J. Spaleta, G. Taylor, J. Timberlake, R. Woolley, L. Zakharov, M. Finkenthal, D. Stutman, L. Delgado-Aparicio, R.P. Seraydarian, G. Antar, R. Doerner, S. Luckhardt, M. Baldwin, R.W. Conn, R. Maingi, M. Menon, R. Causey, D. Buchenauer, M. Ulrickson, B. Jones, and D. Rodgers. Effects of Large Area Liquid Lithium Limiters on Spherical Torus Plasmas. United States: N. p., 2004. Web. doi:10.2172/828014.
R. Kaita, R. Majeski, M. Boaz, P. Efthimion, G. Gettelfinger, T. Gray, D. Hoffman, S. Jardin, H. Kugel, P. Marfuta, T. Munsat, C. Neumeyer, S. Raftopoulos, V. Soukhanovskii, J. Spaleta, G. Taylor, J. Timberlake, R. Woolley, L. Zakharov, M. Finkenthal, D. Stutman, L. Delgado-Aparicio, R.P. Seraydarian, G. Antar, R. Doerner, S. Luckhardt, M. Baldwin, R.W. Conn, R. Maingi, M. Menon, R. Causey, D. Buchenauer, M. Ulrickson, B. Jones, & D. Rodgers. Effects of Large Area Liquid Lithium Limiters on Spherical Torus Plasmas. United States. doi:10.2172/828014.
R. Kaita, R. Majeski, M. Boaz, P. Efthimion, G. Gettelfinger, T. Gray, D. Hoffman, S. Jardin, H. Kugel, P. Marfuta, T. Munsat, C. Neumeyer, S. Raftopoulos, V. Soukhanovskii, J. Spaleta, G. Taylor, J. Timberlake, R. Woolley, L. Zakharov, M. Finkenthal, D. Stutman, L. Delgado-Aparicio, R.P. Seraydarian, G. Antar, R. Doerner, S. Luckhardt, M. Baldwin, R.W. Conn, R. Maingi, M. Menon, R. Causey, D. Buchenauer, M. Ulrickson, B. Jones, and D. Rodgers. Mon . "Effects of Large Area Liquid Lithium Limiters on Spherical Torus Plasmas". United States. doi:10.2172/828014. https://www.osti.gov/servlets/purl/828014.
@article{osti_828014,
title = {Effects of Large Area Liquid Lithium Limiters on Spherical Torus Plasmas},
author = {R. Kaita and R. Majeski and M. Boaz and P. Efthimion and G. Gettelfinger and T. Gray and D. Hoffman and S. Jardin and H. Kugel and P. Marfuta and T. Munsat and C. Neumeyer and S. Raftopoulos and V. Soukhanovskii and J. Spaleta and G. Taylor and J. Timberlake and R. Woolley and L. Zakharov and M. Finkenthal and D. Stutman and L. Delgado-Aparicio and R.P. Seraydarian and G. Antar and R. Doerner and S. Luckhardt and M. Baldwin and R.W. Conn and R. Maingi and M. Menon and R. Causey and D. Buchenauer and M. Ulrickson and B. Jones and D. Rodgers},
abstractNote = {Use of a large-area liquid lithium surface as a first wall has significantly improved the plasma performance in the Current Drive Experiment-Upgrade (CDX-U) at the Princeton Plasma Physics Laboratory. Previous CDX-U experiments with a partially-covered toroidal lithium limiter tray have shown a decrease in impurities and the recycling of hydrogenic species. Improvements in loading techniques have permitted nearly full coverage of the tray surface with liquid lithium. Under these conditions, there was a large drop in the loop voltage needed to sustain the plasma current. The data are consistent with simulations that indicate more stable plasmas having broader current profiles, higher temperatures, and lowered impurities with liquid lithium walls. As further evidence for reduced recycling with a liquid lithium limiter, the gas puffing had to be increased by up to a factor of eight for the same plasma density achieved with an empty toroidal tray limiter.},
doi = {10.2172/828014},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2004},
month = {6}
}