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Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2
Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.
Date:
April 27, 1951
Creator:
Gurinsky, D. H.; Kaplan, I.; Miles, F. T.; Williams, C. & Winsche, W. E.
System:
The UNT Digital Library