The Impact Of Lithium Wall Coatings On NSTX Discharges And The Engineering Of The Lithium Tokamak eXperiment (LTX)

Abstract

Recent experiments on the National Spherical Torus eXperiment (NSTX) have shown the benefits of solid lithium coatings on carbon PFC's to diverted plasma performance, in both Land H-mode confinement regimes. Better particle control, with decreased inductive flux consumption, and increased electron temperature, ion temperature, energy confinement time, and DD neutron rate were observed. Successive increases in lithium coverage resulted in the complete suppression of ELM activity in H-mode discharges. A liquid lithium divertor (LLD), which will employ the porous molybdenum surface developed for the LTX shell, is being installed on NSTX for the 2010 run period, and will provide comparisons between liquid walls in the Lithium Tokamak eXperiment (LTX) and liquid divertor targets in NSTX.LTX, which recently began operations at the Princeton Plasma Physics Laboratory, is the world's first confinement experiment with full liquid metal plasma-facing components (PFCs). All materials and construction techniques in LTX are compatible with liquid lithium. LTX employs an inner, heated, stainless steel-faced liner or shell, which will be lithium-coated. In order to ensure that lithium adheres to the shell, it is designed to operate at up to 500 -600 ºC to promote wetting of the stainless by the lithium, providing the first hot wall in a tokamak to operate at reactor-relevant temperatures. The engineering of LTX will be discussed.

Curvature suppresses the Rayleigh-Taylor instability

“…In such systems it is necessary to protect the plasma and the container wall from each other. It has been suggested that a film of liquid metal offers many advantages over solids as a plasma-facing material [11][12][13][14][15] . For such a system to be successful, it must operate in a regime where the film flowing along the underside of the curved surface remains stable.…”

23rd IAEA Fusion Energy Conference: summary of sessions EX/C and ICC

“…The peaked density profiles are correlated with the presence of a MARFE and a strong density gradient in the edge [56]. LTX is being commissioned to explore the use of liquid lithium wall coatings on a thick conducting segmented wall to improve plasma performance [61]. The extrapolation of these interesting results with lithium to steady state operating conditions and especially to operation with tritium remains to be established.…”