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Liquid Lithium Experiments in CDX-U.

DE2001768653

Publication Date	2000
Personal Author	Majeski, R.; Doerner, R.; Kaita, R.; Antar, G.; Timberlake, J.
Page Count	8
Abstract	The initial results of experiments involving the use of liquid lithium as a plasma facing component in the Current Drive Experiment-Upgrade (CDX-U) are reported. Studies of the interaction of a steady-state plasma with liquid lithium in the Plasma Interaction with Surface and Components Experimental Simulator (PISCES-B) are also summarized. In CDX-U a solid or liquid lithium covered rail limiter was introduced as the primary limiting surface for spherical torus discharges. Deuterium recycling was observed to be reduced, but so far not eliminated, for glow discharge-cleaned lithium surfaces. Some lithium influx was observed during tokamak operation. The PISCES-B results indicate that the rates of plasma erosion of lithium can exceed predictions by an order of magnitude at elevated temperatures. Plans to extend the CDX-U experiments to large area liquid lithium toroidal belt limiters are also described.
Keywords	Lithium Plasmas(Physics) Thermonuclear reactors Deuterium Iaea Italy Nuclear energy Recycling Simulators
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Princeton Univ., NJ. Plasma Physics Lab.; Department of Energy, Washington, DC.
Document Type	Conference Proceedings
NTIS Issue Number	200123
Contract Number	AC02-76CH03073

Liquid Lithium Experiments in CDX-U.

Liquid Lithium Experiments in CDX-U.
DE2001768653

Publication Date	2000
Personal Author	Majeski, R.; Doerner, R.; Kaita, R.; Antar, G.; Timberlake, J.
Page Count	8
Abstract	The initial results of experiments involving the use of liquid lithium as a plasma facing component in the Current Drive Experiment-Upgrade (CDX-U) are reported. Studies of the interaction of a steady-state plasma with liquid lithium in the Plasma Interaction with Surface and Components Experimental Simulator (PISCES-B) are also summarized. In CDX-U a solid or liquid lithium covered rail limiter was introduced as the primary limiting surface for spherical torus discharges. Deuterium recycling was observed to be reduced, but so far not eliminated, for glow discharge-cleaned lithium surfaces. Some lithium influx was observed during tokamak operation. The PISCES-B results indicate that the rates of plasma erosion of lithium can exceed predictions by an order of magnitude at elevated temperatures. Plans to extend the CDX-U experiments to large area liquid lithium toroidal belt limiters are also described.
Keywords	Lithium Plasmas(Physics) Thermonuclear reactors Deuterium Iaea Italy Nuclear energy Recycling Simulators
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Princeton Univ., NJ. Plasma Physics Lab.; Department of Energy, Washington, DC.
Document Type	Conference Proceedings
NTIS Issue Number	200123
Contract Number	AC02-76CH03073