Salt transport extraction of transuranium elements from LWR fuel
Description:
This report discusses a process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl{sub 2} and a Cu-Mg alloy containing not less than about 25% by weight Mg at a temperature in the range of from about 750{degrees}C to about 850{degrees}C to precipitate uranium metal and some of the noble metal fission products leaving the Cu-M…
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Date:
December 31, 1991
Creator:
Pierce, R. D.; Ackerman, J. P.; Battles, J. E.; Johnson, T. R. & Miller, W. E.
Partner:
UNT Libraries Government Documents Department