Highly efficient separation of ruthenium from alkaline radioactive feeds using an anion exchange resin
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Parveen Kumar Verma
Abstract
Ruthenium recovery from the alkaline media was attempted using solid phase extraction. UV-Vis and X-ray absorption studies were performed to understand the ruthenium speciation under different conditions relevant to its extraction from alkaline medium. Since Ru forms anionic complex in the alkaline solution, an anion exchange resin (Dowex 1x8) was selected for its recovery from alkaline media. The precipitation of black RuO2 at the resin surface hinders its back exaction. Experimental conditions were optimized for the quantitative uptake of Ru from alkaline feed and its subsequent back extraction by a series of batch studies. About 90 % of the Ruthenium was back extracted from the resin using alkaline hypochlorite solution and nitric acid solution at different stages in the Ru back extraction cycle. The column studies were done under the optimized condition and showed ~80 % Ru recovery with 5 mL of the eluent (8 M HNO3) and ~90 % recovery in 10 mL including the tailing. The mechanism for the ruthenium extraction from alkaline medium and its back extraction from the resin was proposed.
Acknowledgements
The authors thank Dr. P.K. Pujari, Director, RC& IG and Head, Radiochemistry Division, Bhabha Atomic Research Centre, Mumbai, India for his keen interest in this work. They are also thankful to Dr. S.N. Jha and Dr. D. Bhattacharyya for their help in recording XANES spectra of Ru samples.
Conflict of interest: There is no conflict of interest to declare
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Supplementary Material
The online version of this article offers supplementary material (https://doi.org/10.1515/ract-2019-3182).
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Artikel in diesem Heft
- Frontmatter
- Production of 67Cu by enriched 70Zn targets: first measurements of formation cross sections of 67Cu, 64Cu, 67Ga, 66Ga, 69mZn and 65Zn in interactions of 70Zn with protons above 45 MeV
- Highly efficient separation of ruthenium from alkaline radioactive feeds using an anion exchange resin
- Selective Cs-removal from highly acidic spent nuclear fuel solutions
- Separation and quantification of 90Sr from ion-exchange resin radioactive waste: methods and techniques of analysis
- Separation of radiosilver from a cyclotron-irradiated palladium target
- A novel ionic liquid-impregnated chitosan application for separation and purification of fission 99Mo from alkaline solution
- Formulation of ‘ready-to-use’ human clinical doses of 177Lu-labeled bisphosphonate amide of DOTA using moderate specific activity 177Lu and its preliminary evaluation in human patient
- Possible use of tetrabromophenolphthalein ethyl ester as a liquid dosimeter
Artikel in diesem Heft
- Frontmatter
- Production of 67Cu by enriched 70Zn targets: first measurements of formation cross sections of 67Cu, 64Cu, 67Ga, 66Ga, 69mZn and 65Zn in interactions of 70Zn with protons above 45 MeV
- Highly efficient separation of ruthenium from alkaline radioactive feeds using an anion exchange resin
- Selective Cs-removal from highly acidic spent nuclear fuel solutions
- Separation and quantification of 90Sr from ion-exchange resin radioactive waste: methods and techniques of analysis
- Separation of radiosilver from a cyclotron-irradiated palladium target
- A novel ionic liquid-impregnated chitosan application for separation and purification of fission 99Mo from alkaline solution
- Formulation of ‘ready-to-use’ human clinical doses of 177Lu-labeled bisphosphonate amide of DOTA using moderate specific activity 177Lu and its preliminary evaluation in human patient
- Possible use of tetrabromophenolphthalein ethyl ester as a liquid dosimeter
