Plasma Performance Improvements with Liquid Lithium Limiters in CDX-U
Authors: R. Majeski, M. Boaz, D. Hoffman, B. Jones, R. Kaita, H. Kugel, T. Munsat, J. Spaleta, V. Soukhanovskii, J. Timberlake, L. Zakharov, G. Antar, R. Doerner, S. Luckhardt, R.W. Conn, M. Finkenthal, D. Stutman, R. Maingi, and M. Ulrickson
Date of PPPL Report: July 2002
Submitted to: Fusion Engineering and Design
The use of flowing liquid lithium as a first wall for a reactor has potentially attractive physics and engineering features. The Current Drive eXperiment-Upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has begun experiments with a fully toroidal liquid lithium limiter. CDX-U is a compact [R = 34 cm, a = 22 cm, Btoroidal = 2 kG, IP =100 kA, Te(0) ~ 100 eV, ne(0) ~ 5 x 1019 m-3)] short-pulse (<25 msec) spherical tokamak with extensive diagnostics. The limiter, which consists of a shallow circular stainless steel tray of radius 34 cm and width 10 cm, can be filled with lithium to a depth of a few millimeters, and forms the lower limiting surface for the discharge. Heating elements beneath the tray are used to liquefy the lithium prior to the experiment. The total area of the tray is approximately 2000 cm2. The tokamak edge plasma, when operated in contact with the lithium-filled tray, shows evidence of reduced impurities and recycling. The reduction in recycling and impurities is largest when the lithium is liquefied by heating to 250 degrees Celsius. Discharges which are limited by the liquid lithium tray show evidence of performance enhancement. Radiated power is reduced and there is spectroscopic evidence for increases in the core electron temperature. Furthermore, the use of a liquid lithium limiter reduces the need for conditioning discharges prior to high current operation. The future development path for liquid lithium limiter systems in CDX-U is also discussed.