Extremely Low Recycling and High Power Density Handling in CDX-U Lithium Experiments
Authors: R. Kaita, R. Majeski, R. Doerner, T. Gray, H. Kugel, T. Lynch, R. Maingi, D. Mansfield, V. Soukhanovskii, J. Spaleta, J. Timberlake, and L. Zakharov
Abstract:
The mission of the Current Drive eXperiment-Upgrade (CDX-U) spherical tokamak is to investigate lithium as a plasma-facing component (PFC). The latest CDX-U experiments used a combination of a toroidal liquid lithium limiter and lithium wall coatings applied between plasma shots. Recycling co-efficients for these plasmas were deduced to be 30% or below, and are the lowest ever observed in magnetically-confined plasmas. The corresponding energy confinement times showed nearly a factor of six improvement over discharges without lithium PFC's. An electron beam (e-beam) for evaporating lithium from the toroidal limiter was one of the techniques used to create lithium wall coatings in CDX-U. The evaporation was not localized to the e-beam spot, but occurred only after the entire volume of lithium in toroidal limiter was liquefied. This demonstration of the ability of lithium to handle high heat loads can have significant consequences for PFC's in future burning plasma devices.
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Accepted for publication in: Journal of Nuclear Materials
doi: 10.1016/j.jnucmat.2007.01.229
(Copyright © 2007 Published by Elsevier B.V.)
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Download PPPL-4225 Preprint February 2007 (pdf 1 MB)