Separation of americium from europium using 3,3′-dimethoxy-phenyl-bis-1,2,4-triazinyl-2,6-pyridine

Talon G. Hill, Ai Lin Chin, Serene Tai, Jesse D. Carrick, Dale D. Ensor, Lætitia H. Delmau

Research output: Contribution to journalReview articlepeer-review

26 Scopus citations

Abstract

The development of liquid–liquid separation processes for the effective removal of minor actinide Am(III) from used nuclear fuel (UNF) using ligand-based strategies continues to be an area of significant research focus. The current investigation demonstrates the efficacy of a nitrogen-based bis-triazinyl pyridine (BTP) derivative to selectively extract Am(III) from nitric acid solutions containing light lanthanides. The performance of 3,3ʹ-dimethoxy-phenyl-bis-1,2,4-triazinyl-2,6-pyridine (MOB-BTP) was compared to that of a camphor-substituted BTP (CA-BTP). The results of this investigation demonstrate the novel 3,3ʹ-methoxy-BTP extractant dissolved in a polar diluent was a more efficient extractant for Am(III) at a lower concentration than CA-BTP under comparable conditions.

Original languageEnglish
Pages (from-to)1848-1855
Number of pages8
JournalSeparation Science and Technology (Philadelphia)
Volume53
Issue number12
DOIs
StatePublished - Aug 13 2018

Funding

Financial support for this project was provided by the Fuel Cycle Research and Development program, Office of Nuclear Energy, U.S. Department of Energy and the TTU Department of Chemistry. Support from NSF-RUI 9970016 is acknowledged for the acquisition of the TTU Chemistry Department’s NMR spectrometer. Financial support for this project was provided by the Fuel Cycle Research and Development program, Office of Nuclear Energy, U.S. Department of Energy and the TTU Department of Chemistry. Support from NSF-RUI 9970016 is acknowledged for the acquisition of the TTU Chemistry Department’s NMR spectrometer. Financial support for this project was provided by the Fuel Cycle Research and Development program, Office of Nuclear Energy, U.S. Department of Energy and the TTU

Keywords

  • Americium europium separation
  • BTP
  • nitrogen donor extractant
  • nuclear fuel cycle
  • solvent extraction

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