Effects of Large Area Liquid Lithium Limiters on Spherical Torus Plasmas
Authors: 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
Date of PPPL Report: June 2004
Presented at: the Sixteenth International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI16), Portland, ME, May 24-28, 2004.
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.