부산대학교 도서관

Attention has focused recently on flowing liquid lithium as a first wall for a reactor because of its potentially attractive physics and engineering features. In order to test the suitability of liquid lithium as a plasma facing component, the Current Drive eXperiment - Upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has recently installed a fully toroidal liquid lithium limiter. CDX-U is a compact (R = 34 cm, a = 22 cm, B/sub toroidal/ = 2 kG, I/sub p/ =100 kA, T/sub e/(O) /spl sim/ 100 eV, n/sub e/(0) /spl sim/ 5 /spl times/ 10/sup 19/ m/sup -3/ short-pulse (< 25 msec) spherical torus (ST) with extensive diagnostics. The limiter, which consists of a shallow circular stainless steel tray of radius 34 cm and width 10 cm, is 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 (melting point = 180.5/spl deg/C) prior to the experiment. The total area of liquid lithium exposed to the plasma is approximately 2000 cm/sup 2/. The design of the limiter, modifications to CDX-U to accommodate in-vessel inventories of approximately 1 liter of liquid lithium, techniques for loading lithium onto the limiter, and other preparations will be described. CDX-U has previously been successfully operated with a smaller area cm/sup 2/) liquid lithium rail limiter. Diagnostics specific to lithium operations include multichord spectrometry of the 135 /spl Aring/ LiIII line in the core plasma, monitors for neutral lithium light at the lithium limiter, and a fast (10,000 frame per second) camera which monitors motion of the liquid during the discharge. First results of plasma operations with the toroidal liquid lithium limiter will also be given.