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Flowsheet testing of the Fission Product Extraction Process for the separation of cesium and strontium from spent nuclear fuel

  • Jack D. Law
  • , Dean R. Peterman
  • , Terry A. Todd
  • , David H. Meikrantz
  • , Catherine L. Riddle

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The Fission Product Extraction (FPEX) Process is being developed as part of the United States Department of Energy Advanced Fuel Cycle Initiative for the simultaneous separation of cesium and strontium from spent LWR fuel. Separation of the Cs and Sr will reduce the short-term heat load in a geological repository and, when combined with the separation of Am and Cm, could increase the capacity of the geological repository by a factor of approximately 100. The FPEX process is based on two highly-specific extractants: 4,4□Œ,(5□Œ)-Di-(t-butyldicyclo-hexano)-18-crown-6 (DtBuCH18C6) and Calix[4]arene-bis-(tert-octylbenzo-crown-6) (BOBCalixC6). The DtBuCH18C6 extractant is selective for strontium and the BOBCalixC6 extractant is selective for cesium. Results of flowsheet testing of the FPEX process with simulated feed solution in 3.3-cm centrifugal contactors will be detailed. Removal efficiencies, distribution coefficient data, coextraction of metals, and process hydrodynamic performance will be discussed along with recommendations for future testing.

Original languageEnglish
Title of host publication233rd ACS National Meeting, Abstracts of Scientific Papers
StatePublished - 2007
Event233rd ACS National Meeting - Chicago, IL, United States
Duration: Mar 25 2007Mar 29 2007

Publication series

NameACS National Meeting Book of Abstracts
ISSN (Print)0065-7727

Conference

Conference233rd ACS National Meeting
Country/TerritoryUnited States
CityChicago, IL
Period03/25/0703/29/07

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