Plutonium recovery from spent reactor fuel by uranium displacement
Description:
This report discusses a process for separating uranium values and transuranic values from fission products containing rare earth values when the values which are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytical…
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Date:
December 31, 1991
Creator:
Ackerman, J. P.
Partner:
UNT Libraries Government Documents Department