Magnesium transport extraction of transuranium elements from LWR fuel

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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 uranium concentration and having transuranium actinide metals and rare earth fission product metals and the noble metal fission products ... continued below

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15 p.

Creation Information

Ackerman, J.P.; Battles, J.E.; Johnson, T.R.; Miller, W.E. & Pierce, R.D. December 31, 1991.

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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 uranium concentration and having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein. The CaCl{sub 2} having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO{sub 2}. The Ca metal and CaCl{sub 2} is recycled to reduce additional oxide fuel. The U-Fe alloy having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with Mg metal which takes up the actinide and rare earth fission product metals. The U-Fe alloy retains the noble metal fission products and is stored while the Mg is distilled and recycled leaving the transuranium actinide and rare earth fission products isolated.

Physical Description

15 p.

Notes

INIS; OSTI as DE94003045

Source

  • Other Information: PBD: 1991

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  • Other: DE94003045
  • Report No.: PATENTS-US--A7770387
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 140160
  • Archival Resource Key: ark:/67531/metadc623891

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • December 31, 1991

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • Dec. 15, 2015, 6:15 p.m.

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Citations, Rights, Re-Use

Ackerman, J.P.; Battles, J.E.; Johnson, T.R.; Miller, W.E. & Pierce, R.D. Magnesium transport extraction of transuranium elements from LWR fuel, patent, December 31, 1991; Illinois. (digital.library.unt.edu/ark:/67531/metadc623891/: accessed October 16, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.