Uranium chloride extraction of transuranium elements from LWR fuel

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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 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride ... continued below

Physical Description

16 p.

Creation Information

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

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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 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein.

Physical Description

16 p.

Notes

OSTI as DE94003518

Source

  • Other Information: PBD: 1991

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  • Other: DE94003518
  • Report No.: PATENTS-US--A7770386
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 140356
  • Archival Resource Key: ark:/67531/metadc625165

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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. 15, 2015, 6:26 p.m.

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Citations, Rights, Re-Use

Miller, W.E.; Ackerman, J.P.; Battles, J.E.; Johnson, T.R. & Pierce, R.D. Uranium chloride extraction of transuranium elements from LWR fuel, patent, December 31, 1991; Illinois. (digital.library.unt.edu/ark:/67531/metadc625165/: accessed December 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.