Liquid Lithium Limiter Effects on Tokamak Plasmas and Plasma-Liquid Surface Interactions

Kaita, R. ; Majeski, R. ; Doerner, R. ; Antar, G. ; Baldwin, M. ; Conn, R. ; Efthimion, P. ; Finkenthal, M. ; Hoffman, D. ; Jones, B. ; Krashenninikov, S. ; Kugel, H. ; Luckhardt, S. ; Maingi, R. ; Menard, J. ; Munsat, T. ; Stutman, D. ; Taylor, G. ; Timberlake, J. ; Soukhanovskii, V. ; Whyte, D. ; Woolley, R. ; Zakharov, L.

Princeton University. Plasma Physics Laboratory.

关键词: Vapor Pressure Lithium;    Lithium Deuterides;    Liquid Metals;    Oxygen;    70 Plasma Physics And Fusion Technology;   

DOI  :  10.2172/809848
RP-ID  :  PPPL-3755
RP-ID  :  AC02-76CH03037
RP-ID  :  809848

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来源: UNT Digital Library

【 摘 要 】

We present results from the first experiments with a large area liquid lithium limiter in a magnetic fusion device, and its effect on improving plasma performance by reducing particle recycling. Using large area liquid metal surfaces in any major fusion device is unlikely before a test on a smaller scale. This has motivated its demonstration in the CDX-U spherical torus with a unique, fully toroidal lithium limiter. The highest current discharges were obtained with a liquid lithium limiter. There was a reduction in recycling, as indicated by a significant decrease in the deuterium-alpha emission and oxygen radiation. How these results might extrapolate to reactors is suggested in recycling/retention experiments with liquid lithium surfaces under high-flux deuterium and helium plasma bombardment in PISCES-B. Data on deuterium atoms retained in liquid lithium indicate retention of all incident ions until full volumetric conversion to lithium deuteride. The PISCES-B results also show a material loss mechanism that lowers the maximum operating temperature compared to that for the liquid surface equilibrium vapor pressure. This may restrict the lithium temperature in reactors.