• D. R. Peterman
  • R. S. Herbst
  • J. D. Law
  • R. D. Tillotson
  • T. G. Garn
  • T. A. Todd
  • V. N. Romanovskiy
  • V. A. Babain
  • M. Yu Alyapyshev
  • I. V. Smirnov

The Universal Extraction (UNEX) process has been developed for simultaneous extraction of cesium, strontium, and actinides from acidic solutions. This process utilizes an extradant consisting of 0.08 M chlorinated cobalt dicarbollide (HCCD), 0.007-0.02 M polyethylene glycol (PEG-400), and 0.02 M diphenyl-N,N-di-n-butylcarbamoylmethylphosphine oxide (PhiCMPO) in the diluent trifluoromethylphenyl sulfone (CF3C6H5SO 2, designated FS-13) and provides simultaneous extraction of Cs, Sr, actinides, and lanthanides from HNO3 solutions. The UNEXprocess is of limited utility for processing acidic solutions containing large quantities of lanthanides and/or actinides, such as dissolved spent nuclear fuel solutions. These constraints are primarily attributed to the limited concentrations of CMPO (a maximum of ∼0.02 M) in the organic phase and limited solubility of the CMPO-metal complexes. As a result, alternative actinide and lanthanide extradants are being investigated for use with HCCD as an improvement for waste processing and for applications where higher concentrations of the metals are present. Our preliminary results indicate that diamide derivatives of dipicolinic acid may function as efficient actinide and lanthanide extradants. The results to be presented indicate that, of the numerous diamides studied to date, the tetrabutyldiamide of dipicolinic acid, TBDPA, shows the most promise as an alternative adinide/lanthanide extradant in the UNEX process.

Original languageEnglish
Title of host publicationGLOBAL 2007
Subtitle of host publicationAdvanced Nuclear Fuel Cycles and Systems
Pages1106-1110
Number of pages5
StatePublished - 1 Dec 2007
EventGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems - Boise, ID, United States
Duration: 9 Sep 200713 Sep 2007

Publication series

NameGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems

Conference

ConferenceGLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems
Country/TerritoryUnited States
CityBoise, ID
Period9/09/0713/09/07

    Scopus subject areas

  • Energy Engineering and Power Technology
  • Fuel Technology
  • Nuclear Energy and Engineering

ID: 42868506