A conceptual study of a tokamak reactor with liquid lithium and with evaporative cooling and protectio of the blanket and the divertor has been conduced and its advantages are discussed. Up to now, no self-consistent solution of the problem of the divertor has bene found for ITER conditions, and it is not likely to be found during the ITER Engineering Design Activities (EDA). The little space left after allowing for the magnetic coil systems, auxiliary heating, diagnostics, and the blanket tritium breeding and cooling system does not permit use of an ordinary cooling system, as used i a fission reactor, at a fusion power level of over 1.5 GW. The following issues have bene considered in the Liquid Lithium Fusion Reactor project: the necessity of liquid metla for the development of a tokamak based reactor to produce electricity, the advantages of lithium, possible fabrication solutions for the liquid metal blanket and divertor systems, reactor structural materials, reactor safety, and tritium and helium extraction. Along with the concetual design studies, the paper presents results of calculations and experiments aimed at reactor validation.
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