Abstract
The most important issues for steady-state operation of magnetic fusion devices are plasma facing components. Usual materials as graphite, beryllium, tungsten don’t decide this problem. Liquid lithium may be considered as possible plasma facing material in magnetic fusion devices. The lithium capillary target experiments in Russia with the electron beam on SPRUT-4 DEVICE, experiments simulating the disruption conditions in a tokamak, and on tokamak T-11M and calculations of the lithium ions behavior in tokamak have been performed at last years. This concept assumes the evaporational-radiational cooling of highest loaded elements.
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© 2000 Springer Science+Business Media Dordrecht
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Pistunovich, V.I. (2000). Wall Pumping in Tokamak with Lithium. In: Wu, C.H. (eds) Hydrogen Recycling at Plasma Facing Materials. NATO Science Series, vol 1. Springer, Dordrecht. https://doi.org/10.1007/978-94-011-4331-8_6
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DOI: https://doi.org/10.1007/978-94-011-4331-8_6
Publisher Name: Springer, Dordrecht
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