Abstract
The present work investigates the role of increase in the basicity of organophosphorus extractant (dialkylalkyl phosphonates) on the uptake of actinides and fission products vis-à-vis tributyl phosphate (TBP), currently employed as a universal extractant. Two dialkylalkyl phosphonates viz. dibutylpropyl phosphonate (DBPrP) and dibutylpentyl phosphonate (DBPeP) were synthesized, characterized and evaluated for their solvent extraction behavior towards U(VI), Th(IV), Eu(III) and Tc(VII) in nitric acid medium ranging from 0.01–6 M. It was observed that increasing the basicity of the phosphoryl oxygen enhanced the uptake of the actinides and the distribution coefficient values were significantly larger as compared to TBP. The limiting organic concentration (LOC) value was estimated for Th(IV) for these extractants and compared with the TBP system. The separation factors of actinides with phosphonates over Tc(VII) are distinctly better than that with TBP.
Acknowledgement
This research was supported by World Class University (WCU) program to V. K. M. through the National Research Foundation of Korea (NRF) funded by Ministry of Education, Science and Technology (R31-2008-10029). One of the authors (C. K. V.) would like to thank Director IGCAR, India for permission to carry out work at RCL, IGCAR, India.
©2014 Walter de Gruyter Berlin/Boston
Articles in the same Issue
- Frontmatter
- Preface
- Separation Science in Nuclear Technology in India
- Studies on extraction of actinides by unsymmetrical diamylbutyl phosphonate
- Supercritical fluid extraction of uranium and thorium from nitric acid medium using organophosphorous compounds
- Novel polymer inclusion membranes containing T2EHDGA as carrier extractant for actinide ion uptake from acidic feeds
- Studies on the feasibility of using completely incinerable reagents for the single-cycle separation of americium(III) from simulated high-level liquid waste
- Phosphonates as alternative to tributyl phosphate for the separation of actinides from fission products
- Actinides draw down process for pyrochemical reprocessing of spent metal fuel
- Spectroscopic investigations on sorption of uranium onto suspended bentonite: effects of pH, ionic strength and complexing anions
- Speciation of citric acid on anatase (TiO2)–water interface and its effect on Eu(III) sorption
- Separation of 134Cs and 137Cs from 125I solution for medical applications
- Optimization of 210Po estimation in environmental samples using an improved deposition unit
Articles in the same Issue
- Frontmatter
- Preface
- Separation Science in Nuclear Technology in India
- Studies on extraction of actinides by unsymmetrical diamylbutyl phosphonate
- Supercritical fluid extraction of uranium and thorium from nitric acid medium using organophosphorous compounds
- Novel polymer inclusion membranes containing T2EHDGA as carrier extractant for actinide ion uptake from acidic feeds
- Studies on the feasibility of using completely incinerable reagents for the single-cycle separation of americium(III) from simulated high-level liquid waste
- Phosphonates as alternative to tributyl phosphate for the separation of actinides from fission products
- Actinides draw down process for pyrochemical reprocessing of spent metal fuel
- Spectroscopic investigations on sorption of uranium onto suspended bentonite: effects of pH, ionic strength and complexing anions
- Speciation of citric acid on anatase (TiO2)–water interface and its effect on Eu(III) sorption
- Separation of 134Cs and 137Cs from 125I solution for medical applications
- Optimization of 210Po estimation in environmental samples using an improved deposition unit