Salt 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 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-Mg alloy having transuranium actinide metals and rare earth fission product metals and some of the noble metal ... continued below

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16 p.

Creation Information

Pierce, R.D.; Ackerman, J.P.; Battles, J.E.; Johnson, T.R. & Miller, W.E. 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 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-Mg alloy having transuranium actinide metals and rare earth fission product metals and some of 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 Cu-Mg alloy having transuranium metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with a transport salt including Mg C1{sub 2} to transfer Mg values from the transport salt to the Cu-Mg alloy .hile transuranium actinide and rare earth fission product metals transfer from the Cu-Mg alloy to the transport salt. Then the transport salt is mixed with a Mg-Zn alloy to transfer Mg values from the alloy to the transport salt while the transuranium actinide and rare earth fission product values dissolved in the salt are reduced and transferred to the Mg-Zn alloy.

Physical Description

16 p.

Notes

INIS; OSTI as DE94003046

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  • Other Information: PBD: 1991

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  • Other: DE94003046
  • Report No.: PATENTS-US--A7770385
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 140161
  • Archival Resource Key: ark:/67531/metadc619251

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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.

Description Last Updated

  • Dec. 14, 2015, 11:43 a.m.

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Pierce, R.D.; Ackerman, J.P.; Battles, J.E.; Johnson, T.R. & Miller, W.E. Salt transport extraction of transuranium elements from LWR fuel, patent, December 31, 1991; Illinois. (digital.library.unt.edu/ark:/67531/metadc619251/: accessed December 11, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.