Uranium chloride extraction of transuranium elements from LWR fuel Metadata

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Title

  • Main Title Uranium chloride extraction of transuranium elements from LWR fuel

Creator

  • Author: Miller, W.E.
    Creator Type: Personal
  • Author: Ackerman, J.P.
    Creator Type: Personal
  • Author: Battles, J.E.
    Creator Type: Personal
  • Author: Johnson, T.R.
    Creator Type: Personal
  • Author: Pierce, R.D.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE, Washington, DC (United States)

Publisher

  • Name: Argonne National Laboratory
    Place of Publication: Illinois
    Additional Info: Argonne National Lab., IL (United States)

Date

  • Creation: 1991-12-31

Language

  • English

Description

  • Content 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.

Subject

  • Keyword: Transuranium Elements
  • Keyword: Reprocessing
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Uranium Chlorides
  • Keyword: Spent Fuels
  • Keyword: Solvent Extraction
  • STI Subject Categories: 40 Chemistry

Source

  • Other Information: PBD: 1991

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Rights

  • Patent Assignee: USDOE, Washington, DC (United States)

Resource Type

  • Patent

Format

  • Text

Identifier

  • 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

Note

  • Display Note: OSTI as DE94003518