NSTX Plasma Operation with a Liquid Lithium Divertor
Authors: H.W. Kugel, J.P. Allain, M.G. Bell, R.E. Bell, A. Diallo, R. Ellis, S.P. Gerhardt, B. Heim, M.A. Jaworski, R. Kaita, J. Kallman, S. Kaye, B.P. LeBlanc, R. Maingi, A. McLean, J. Menard, D. Mueller, R. Nygren, M. Ono, S.F. Paul, R. Raman, A.L. Roquemore, S.A. Sabbagh, H. Schneider, C.H. Skinner, V.A. Soukhanovskii, C.N. Taylor, J.R. Timberlake, M. Viola, L. Zakharov, and the NSTX Research Team
Abstract:
NSTX 2010 experiments were conducted using a molybdenum Liquid Lithium Divertor (LLD) surface installed on the
outer part of the lower divertor. This tested the effectiveness of maintaining the deuterium retention properties of a static
liquid lithium surface when refreshed by lithium evaporation as an approximation to a flowing liquid lithium surface. The
LLD molybdenum front face has a 45% porosity to provide sufficient wetting to spread 37 g of lithium, and to retain it in
the presence of magnetic forces. Lithium Evaporators were used to deposit lithium on the LLD surface. At the beginning
of discharges, the LLD lithium surface ranged from solid to liquefied depending on the amount of applied and plasma
heating. Noteworthy improvements in plasma performance were obtained similar to those obtained previously with
lithiated graphite, e.g., ELM-free, quiescent edge, H-modes. During these experiments with the plasma outer strike point
on the LLD, the rate of deuterium retention in the LLD, as indicated by the fueling needed to achieve and maintain stable
plasma conditions, was the about the same as that for solid lithium coatings on the graphite prior to the installation of the
LLD, i.e ., about two times that of no-lithium conditions. The role of lithium impurities in this result is discussed.
Following the 2010 experimental campaign, inspection of the LLD found mechanical damage to the plate supports, and
other hardware resulting from forces following plasma current disruptions. The LLD was removed, upgraded, and
reinstalled. A row of molybdenum tiles was installed inboard of the LLD for 2011 experiments with both inner and outer
strike points on lithiated molybdenum to allow investigation of lithium plasma facing issues encountered in the first testing
of the LLD.
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Submitted to: Fusion Engineering and Design (May 2011)
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