Plutonium recovery from spent reactor fuel by uranium displacement Page: 9 of 20
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8
plutonium transferred from the anode causing the electrolyte
to have a second ratio of plutonium chloride to uranium
chloride larger than the first ratio, removing the solid
cathode with the uranium metal deposited thereon and
dissolving some of the uranium metal in molten cadmium,
contacting the molten cadmium with uranium values dissolved
therein with the molten salt electrolyte having the second
ratio, and chemically transferring plutonium values from the
electrolyte to the molten cadmium and transferring uranium
10 values from the molten cadmium to the electrolyte until the
first ratio of plutonium chloride to uranium chloride is
reestablished.
The invention consists of certain novel features and a
combination of parts hereinafter fully described, and
particularly pointed out in the appended claims, it being
understood that various changes in the details may be made
without departing from the spirit, or sacrificing any of the
advantages of the present invention.
Detailed Description Of The Invention
20 These and other objects of the invention for\ recovering
uranium and transuranic values from spent fuel elements and
separating those values from rare earth fission product
values when these values are contained together in a fused
chloride salt may be met by first electrolytically
transferring the values from the metal state into the
electrolyte salt and thereafter chemically transferring
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Ackerman, J. P. Plutonium recovery from spent reactor fuel by uranium displacement, patent, December 31, 1991; Illinois. (https://digital.library.unt.edu/ark:/67531/metadc1314596/m1/9/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.