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This document describes a molten salt reactor that uses uranium or thorium fluoride dissolved in fluoride salt as fuel, with a graphite moderator. It has an outlet temperature of 700°C, negative temperature coefficient reactivity, capacity of 1000 MWe, and operates at low pressure below 0.5 MPa. Benefits include efficient heat removal, reduced core size due to less pumping and piping needs, proliferation resistance through low fissile material inventory, waste minimization, and efficient uranium use. Timelines and cost comparisons for molten salt reactors are also mentioned.






