Title
Effects of large area liquid lithium limiters on spherical torus plasmas
Date Issued
01 March 2005
Access level
open access
Resource Type
conference paper
Author(s)
Kaita R.
Majeski R.
Boaz M.
Efthimion P.
Gettelfinger G.
Gray T.
Hoffman D.
Jardin S.
Kugel H.
Marfuta P.
Munsat T.
Neumeyer C.
Raftopoulos S.
Soukhanovskii V.
Spaleta J.
Taylor G.
Timberlake J.
Woolley R.
Zakharov L.
Finkenthal M.
Stutman D.
Seraydarian R.P.
Antar G.
Doerner R.
Luckhardt S.
Baldwin M.
Conn R.W.
Maingi R.
Menon M.
Causey R.
Buchenauer D.
Ulrickson M.
Jones B.
Rodgers D.
Johns Hopkins University
Abstract
Use of a large-area liquid lithium surface as a limiter 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. © 2004 Elsevier B.V. All rights reserved.
Start page
872
End page
876
Volume
337-339
Issue
1-3 SPEC. ISS.
Language
English
OCDE Knowledge area
Física de partículas, Campos de la Física Física de plasmas y fluídos
Scopus EID
2-s2.0-13844318528
ISSN of the container
00223115
Conference
Journal of Nuclear Materials
Sponsor(s)
This work was supported by the US Department of Energy in part under Contract DE-AC02-76-CHO3073.
Sources of information: Directorio de Producción Científica Scopus