Back to Search Start Over

Effects of large area liquid lithium limiters on spherical torus plasmas

Authors :
R. Kaita
Robert W. Conn
G. Taylor
M.J. Baldwin
Tobin Munsat
Vlad Soukhanovskii
C. Neumeyer
T.K. Gray
L. F. Delgado-Aparicio
J. Spaleta
R. Woolley
B. Jones
Rajesh Maingi
D. Rodgers
G. Gettelfinger
Michael Finkenthal
G. Antar
Stephen Jardin
Russ Doerner
D. Hoffman
M.M. Menon
R. Majeski
M. Boaz
J. Timberlake
S. C. Luckhardt
Leonid E. Zakharov
M.A. Ulrickson
P. C. Efthimion
H.W. Kugel
Dan Stutman
R. P. Seraydarian
S. Raftopoulos
P. Marfuta
R. Causey
D. Buchenauer
Source :
Journal of Nuclear Materials. :872-876
Publication Year :
2005
Publisher :
Elsevier BV, 2005.

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.

Details

ISSN :
00223115
Database :
OpenAIRE
Journal :
Journal of Nuclear Materials
Accession number :
edsair.doi...........ce18fe7b74da08f45b01d5c0ad6b85a0
Full Text :
https://doi.org/10.1016/j.jnucmat.2004.10.019