Development of Acetic Acid Removal Technology for the UREX+Process Metadata

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  • Main Title Development of Acetic Acid Removal Technology for the UREX+Process


  • Author: Counce, Robert M.
    Creator Type: Personal
  • Author: Watson, Jack S.
    Creator Type: Personal


  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization


  • Name: University of Tennessee/Chemical and Biomolecular Engineering Department
    Place of Publication: United States


  • Creation: 2009-06-30


  • English


  • Content Description: It is imperative that acetic acid is removed from a waste stream in the UREX+process so that nitric acid can be recycled and possible interference with downstreatm steps can be avoidec. Acetic acid arises from acetohydrozamic acid (AHA), and is used to suppress plutonium in the first step of the UREX+process. Later, it is hydrolyzed into hydroxyl amine nitrate and acetic acid. Many common separation technologies were examined, and solvent extraction was determined to be the best choice under process conditions. Solvents already used in the UREX+ process were then tested to determine if they would be sufficient for the removal of acetic acid. The tributyl phosphage (TBP)-dodecane diluent, used in both UREX and NPEX, was determined to be a solvent system that gave sufficient distribution coefficients for acetic acid in addition to a high separation factor from nitric acid.


  • Keyword: Removal
  • Keyword: Modifications
  • Keyword: Uranium
  • Keyword: Recycling
  • Keyword: Radioactive Waste Processing
  • Keyword: Purex Process
  • Keyword: Nitric Acid
  • STI Subject Categories: 11 Nuclear Fuel Cycle And Fuel Materials
  • Keyword: Solvents
  • Keyword: Solvent Extraction
  • STI Subject Categories: 12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities
  • Keyword: Acetic Acid


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


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report


  • Text


  • Report No.: DOE/ID/14735
  • Grant Number: FC07-06ID14735
  • DOI: 10.2172/962149
  • Office of Scientific & Technical Information Report Number: 962149
  • Archival Resource Key: ark:/67531/metadc927996