Methods For Separating Actinides From Reprocessing And Refabrication Plant Wastes

  • D. W. Tedder
  • B. C. Finney
  • J. O. Blomeke
Part of the Advances in Nuclear Science & Technology book series (ANST)


Chemical processing flowsheets have been developed to partition actinides from all actinide-bearing LWR fuel reprocessing and refabrication plant wastes. These wastes include high-activity-level liquids, scrap recovery liquors, HEPA filters and incinerator ashes, and chemical salt wastes such as sodium carbonate scrub solutions, detergent cleanup streams, and alkaline off-gas scrubber liquors. The separation processes that were adopted for this study are based on solvent extraction, cation exchange chromatography, and leaching with Ce4 +-HNO3 solution.


Cation Exchange Chromatography Fuel Reprocess High Level Liquid Waste Nuclear Waste Management Trivalent Actinide 
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  1. 1.
    J. O. Blomeke, “A Program to Establish the Technical Feasibility and Inc“En”tives for Partitioning” Managem“En”t of Radioactive Waste: Waste Partitioning as an Alternative NR-CONF-001 (1976).Google Scholar
  2. 2.
    A. G. Croff, D. W. Tedder, J. P. Drago, J. O. Blomeke, and J. J. Perona, A Preliminary Assessm“En”t of Partitioning and Transmutation as a Radioactive Waste Managem“En”t Concept, ORNL/TM-5808, Oak Ridge National Laboratory, Oak Ridge, TN (1977).Google Scholar
  3. 3.
    D. W. Tedder, B. C. Finney, and J. O. Blomeke, Actinide Partitioning-Transmutation Program Final Report II. Partitioning Processes for LWR Fuel Reprocessing & Refabrication Plant Wastes, ORNL/T1–6982, Oak Ridge National Laboratory, Oak Ridge, TN (In Press).Google Scholar
  4. 4.
    L. D. Mclsaac, J. D. Baker, J. F. Krupa, R. E. LaPointe, D. H. Meikrantz, and N. C. Schroeder, Study of Bidentate Compounds for Separation of Actinides from Commercial LWR Reprocessing Wastes, ICP-1180, Idaho National “En”gineering Laboratory, Idaho Falls, Idaho (1979).Google Scholar
  5. 5.
    F. M. Scheitlin and W. D. Bond, Recovery of Plutonium from HEPA Filter Media by Continuously Leaching in a Packed Column with Electrolytically Produced Ce(IV) Nitrate and Nitric Acid,ORNL/TM-6802, Oak Ridge National Laboratory, Oak Ridge, TN (In Press).Google Scholar
  6. 6.
    G. H. Thompson, Final Report - Program for Waste Management Analysis of the Nuclear Fuel Cycle - ORNL Actinide Recovery from Combustible Waste: The Ce(IV)-HNO 3 System, RFP-2907, Rocky Flats Plant, Gold“En”, CO (In Press).Google Scholar
  7. 7.
    E. J. Wheelwright, L. A. Bray, H. H. Van Tuyl, and H. T. Fullam, Flowsheet for Recovery of Curium from Power Reactor Fuel Reprocessing Plant Waste, BNWL-1831, Battelle Pacific Northwest Laboratory, Richland, WA (1974).Google Scholar
  8. 8.
    C. W. Forsberg, The Elution Sequence of Neptunium and Plutonium from a Cation Exchange Chromatography Column Eluted with Diethylenetriaminep“En”taacetic Acid (DTPA), ORNL/TM-6737, Oak Ridge National Laboratory, Oak Ridge, TN (1979).Google Scholar
  9. 9.
    E. P. Horwitz, C. A. A. Bloomquist, G. W. Mason, R. A. Leonard, and A. A. Ziegler, The Recovery of Actinides from TBP-Na2CO3 Scrub Waste Solutions: The Aralex Process, ANL-79–74, Argonne National Laboratory, Argonne, IL (1979).Google Scholar

Copyright information

© Springer Science+Business Media New York 1980

Authors and Affiliations

  • D. W. Tedder
    • 1
  • B. C. Finney
    • 1
  • J. O. Blomeke
    • 1
  1. 1.Oak Ridge National LaboratoryOak RidgeUSA

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