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Development of the universal extraction (UNEX) process for the simultaneous recovery of Cs, Sr, and actinides from acidic radioactive wastes

  • R. Scott Herbst
  • , Jack D. Law
  • , Terry A. Todd
  • , V. N. Romanovskiy
  • , I. V. Smirnov
  • , V. A. Babain
  • , V. N. Esimantovskiy
  • , B. N. Zaitsev

Research output: Contribution to journalArticlepeer-review

54 Scopus citations

Abstract

A synergistic extraction mixture containing chlorinated cobalt dicarbollide (CCD), polyethylene glycol (PEG), and diphenyl-N,N-dibutylcarbamoyl phosphine oxide (CMPO) in a suitable polar diluent is being developed for the simultaneous recovery of Cs, Sr, and the actinides from highly acidic radioactive wastes. Development of this UNEX process was by a successful collaboration between scientists from the Idaho National Engineering and Environmental Laboratory (INEEL) and the Khlopin Radium Institute (KRI) in St. Petersburg, Russia. Development efforts focused on the treatment of radioactive waste currently stored at the INEEL. The development of the UNEX process has and continues to be an evolutionary process. Numerous countercurrent flowsheet demonstrations have been conducted to date, including two tests with several liters of actual radioactive tank waste, one test with dissolved radioactive calcine, and several tests with surrogate INEEL tank and dissolved calcine wastes. All countercurrent flowsheet tests have been performed in banks of centrifugal contactors. Removal efficiencies of 99.95% for 137Cs, 99.995% for 90Sr, and 99.96% for total α (predominately 241Am, 238Pu, and 239Pu) were observed in countercurrent tests with samples of actual INEEL tank waste. The evolutionary concepts included in the development of the UNEX process are discussed, including development of the current diluent, phenyltrifluoromethyl sulfone, to replace nitroaromatic diluents used in earlier studies. Results from the most recent countercurrent flowsheet testing with 1.2 L of actual dissolved INEEL calcine are also presented, which represents the current state of UNEX development. Finally, future research directions in the development and understanding of the UNEX process are discussed.

Original languageEnglish
Pages (from-to)2685-2708
Number of pages24
JournalSeparation Science and Technology
Volume38
Issue number12-13
DOIs
StatePublished - 2003

Keywords

  • Actinide removal
  • Cesium removal
  • High-level radioactive waste
  • Solvent extraction
  • Strontium removal

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