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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… more
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
open access

Process to remove rare earth from IFR electrolyte

Description: The invention is a process for the removal of rare earths from molten chloride electrolyte salts used in the reprocessing of integrated fast reactor fuel (IFR). The process can be used either continuously during normal operation of the electrorefiner or as a batch process. The process consists of first separating the actinide values from the salt before purification by removal of the rare earths. After replacement of the actinides removed in the first step, the now-purified salt electrolyte has… more
Date: January 1, 1992
Creator: Ackerman, J. P. & Johnson, T. R.
Partner: UNT Libraries Government Documents Department
open access

Uranium chloride extraction of transuranium elements from LWR fuel

Description: A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800{degrees}C to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride… more
Date: December 31, 1991
Creator: Miller, W. E.; Ackerman, J. P.; Battles, J. E.; Johnson, T. R. & Pierce, R. D.
Partner: UNT Libraries Government Documents Department
open access

Magnesium 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 U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800{degrees}C to about 850{degrees}C to produce additional uranium metal which dissolves in the U-Fe alloy raising the uran… more
Date: December 31, 1991
Creator: Ackerman, J. P.; Battles, J. E.; Johnson, T. R.; Miller, W. E. & Pierce, R. D.
Partner: UNT Libraries Government Documents Department
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