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Title: Recent Liquid Lithium Limiter Experiments in CDX-U

Abstract

Recent experiments in the Current Drive eXperiment-Upgrade (CDX-U) provide a first-ever test of large area liquid lithium surfaces as a tokamak first wall, to gain engineering experience with a liquid metal first wall, and to investigate whether very low recycling plasma regimes can be accessed with lithium walls. The CDX-U is a compact (R=34 cm, a=22 cm, B{sub toroidal} = 2 kG, I{sub P} =100 kA, T{sub e}(0) {approx} 100 eV, n{sub e}(0) {approx} 5 x 10{sup 19} m{sup -3}) spherical torus at the Princeton Plasma Physics Laboratory. A toroidal liquid lithium pool limiter with an area of 2000 cm{sup 2} (half the total plasma limiting surface) has been installed in CDX-U. Tokamak discharges which used the liquid lithium pool limiter required a fourfold lower loop voltage to sustain the plasma current, and a factor of 5-8 increase in gas fueling to achieve a comparable density, indicating that recycling is strongly reduced. Modeling of the discharges demonstrated that the lithium limited discharges are consistent with Z{sub effective} < 1.2 (compared to 2.4 for the pre-lithium discharges), a broadened current channel, and a 25% increase in the core electron temperature. Spectroscopic measurements indicate that edge oxygen and carbon radiation are stronglymore » reduced.« less

Authors:
; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Princeton Plasma Physics Lab., Princeton, NJ (US)
Sponsoring Org.:
USDOE Office of Science (SC) (US)
OSTI Identifier:
839533
Report Number(s):
PPPL-4068
TRN: US0501747
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 3 May 2005
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; CARBON; ELECTRIC CURRENTS; ELECTRON TEMPERATURE; FIRST WALL; LIQUID METALS; LITHIUM; OXYGEN; PHYSICS; PLASMA; RADIATIONS; RECYCLING; SIMULATION; EDGE PLASMA; TOKAMAKS

Citation Formats

R. Majeski, S. Jardin, R. Kaita, T. Gray, P. Marfuta, J. Spaleta, J. Timberlake, L. Zakharov, G. Antar, R. Doerner, S. Luckhardt, R. Seraydarian, V. Soukhanovskii, R. Maingi, M. Finkenthal, D. Stutman, D. Rodgers, and S. Angelini. Recent Liquid Lithium Limiter Experiments in CDX-U. United States: N. p., 2005. Web. doi:10.2172/839533.
R. Majeski, S. Jardin, R. Kaita, T. Gray, P. Marfuta, J. Spaleta, J. Timberlake, L. Zakharov, G. Antar, R. Doerner, S. Luckhardt, R. Seraydarian, V. Soukhanovskii, R. Maingi, M. Finkenthal, D. Stutman, D. Rodgers, & S. Angelini. Recent Liquid Lithium Limiter Experiments in CDX-U. United States. doi:10.2172/839533.
R. Majeski, S. Jardin, R. Kaita, T. Gray, P. Marfuta, J. Spaleta, J. Timberlake, L. Zakharov, G. Antar, R. Doerner, S. Luckhardt, R. Seraydarian, V. Soukhanovskii, R. Maingi, M. Finkenthal, D. Stutman, D. Rodgers, and S. Angelini. Tue . "Recent Liquid Lithium Limiter Experiments in CDX-U". United States. doi:10.2172/839533. https://www.osti.gov/servlets/purl/839533.
@article{osti_839533,
title = {Recent Liquid Lithium Limiter Experiments in CDX-U},
author = {R. Majeski and S. Jardin and R. Kaita and T. Gray and P. Marfuta and J. Spaleta and J. Timberlake and L. Zakharov and G. Antar and R. Doerner and S. Luckhardt and R. Seraydarian and V. Soukhanovskii and R. Maingi and M. Finkenthal and D. Stutman and D. Rodgers and S. Angelini},
abstractNote = {Recent experiments in the Current Drive eXperiment-Upgrade (CDX-U) provide a first-ever test of large area liquid lithium surfaces as a tokamak first wall, to gain engineering experience with a liquid metal first wall, and to investigate whether very low recycling plasma regimes can be accessed with lithium walls. The CDX-U is a compact (R=34 cm, a=22 cm, B{sub toroidal} = 2 kG, I{sub P} =100 kA, T{sub e}(0) {approx} 100 eV, n{sub e}(0) {approx} 5 x 10{sup 19} m{sup -3}) spherical torus at the Princeton Plasma Physics Laboratory. A toroidal liquid lithium pool limiter with an area of 2000 cm{sup 2} (half the total plasma limiting surface) has been installed in CDX-U. Tokamak discharges which used the liquid lithium pool limiter required a fourfold lower loop voltage to sustain the plasma current, and a factor of 5-8 increase in gas fueling to achieve a comparable density, indicating that recycling is strongly reduced. Modeling of the discharges demonstrated that the lithium limited discharges are consistent with Z{sub effective} < 1.2 (compared to 2.4 for the pre-lithium discharges), a broadened current channel, and a 25% increase in the core electron temperature. Spectroscopic measurements indicate that edge oxygen and carbon radiation are strongly reduced.},
doi = {10.2172/839533},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue May 03 00:00:00 EDT 2005},
month = {Tue May 03 00:00:00 EDT 2005}
}

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