Novel polymer inclusion membranes containing T2EHDGA as carrier extractant for actinide ion uptake from acidic feeds
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Bholanath Mahanty
, Dhaval Ramakant Raut
Abstract
Polymer inclusion membranes (PIM) containing N,N,N′,N′-tetra(2-ethylhexyl) diglycolamide (T2EHDGA) were evaluated for the separation of actinide ions such as Am3+, Pu4+, UO22+ and Th4+ from acidic feeds. The PIMs were prepared using cellulose triacetate (CTA) as the polymer matrix, 2-nitrophenyloctyl ether (NPOE) as the plasticizer and T2EHDGA as the carrier extractant and the optimized membrane composition was found to be 68.4% T2EHDGA, 17.9% NPOE and 13.7% CTA which resulted in 74% Am3+ uptake at 1 M HNO3 in 2 h. The uptake studies were carried out using feed solutions containing varying concentrations of nitric acid (0.5–3.0 M) and showed the trend: Pu4+ > Am3+ > Th4+ > UO22+. Quantitative stripping (> 99%) of the sorbed Am3+ was possible using a solution containing 0.01 M EDTA at pH 3.0. Reusability studies indicated deterioration of the PIM on continuous use.
Acknowledgement
The authors (DRR, BNM and PKM) thank Dr. A. Goswami, Head Radiochemistry Division, BARC for his constant encouragement.
©2015 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
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- 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