Published July 2010 | Version v1
Journal article

Separation of uranium from different uranium oxide matrices employing supercritical carbon dioxide extraction

  • 1. Bhabha Atomic Research Centre, Trombay (India). Radioanalytical Chemistry Division, Chemistry Division

Description

Uranium from different uranium oxide matrices was extracted with tri-n-butyl phosphate-nitric acid (TBP-HNO3) adduct using supercritical carbon dioxide (SC CO2). While 30 min dissolution time at 323 K was sufficient for U3O8 and UO2 powder, UO2 granule (at 333 K) and crushed green pellet (at 353 K) required 40 min. Crushed sintered pellet required 60 min at 353 K for complete dissolution. Influence of various experimental parameters such as temperature, pressure, volume of TBP-HNO3 adduct, acidity of nitric acid used for preparing TBP-HNO3 adduct and extraction time on uranium extraction efficiency was also investigated. For UO2 powder, temperature of 323 K, pressure of 15.2 MPa, 1 mL TBP-HNO3 adduct, 10 M nitric acid and 30 min extraction time was found to be optimum. ∼70% uranium extraction efficiency was obtained on extraction with SC CO2 alone which increased to 90% with the addition of 2.5% TBP in SC CO2 stream. Extraction efficiency was found to vary linearly with TBP percentage and nearly complete uranium extraction (∼99%) was observed with 20% TBP. Nearly complete extraction was also achieved with addition of 2.5% thenoyltrifluoroacetylacetone (TTA) in methanol. The optimized procedure was extended to remove uranium from simulated tissue paper waste matrix smeared with uranium oxide solids. (author)

Additional details

Publishing Information

Journal Title
Journal of Radioanalytical and Nuclear Chemistry
Journal Volume
285
Journal Issue
2
Journal Page Range
p. 247-257
ISSN
0236-5731
CODEN
JRNCDM

Optional Information

Notes
23 refs.