Separation and quantification of 90Sr from ion-exchange resin radioactive waste: methods and techniques of analysis
-
Aurelia Magdalena Dianu
and
Relu Ion Dobrin
Abstract
Four methods for 90Sr separation from spent ion-exchange resin samples were carried out, offering a useful methodology to achieve interferences free 90Sr fractions. The four methods consist in resin sample decomposition, pre-treatment and selective separation of 90Sr by using: (a) a single chromatographic extraction process, (b) double chromatographic extraction, (c) a single chromatographic extraction process followed in sequence by two precipitations, and (d) ion-exchange chromatography, followed by extraction chromatography and precipitation. Mineralization by microwave acid digestion and the four 90Sr separation methods thoroughly presented are available. Data processing methods (adjustable modified efficiency tracing – a new improved approach for the efficiency tracing LSC technique, non-linear regression and α-β discrimination) to obtain the activities values of α, β-γ, pure β emitters and the evaluation of chemical recovery yield of strontium were presented. A discussion about activity assessment in 90Sr purified fractions, providing a convincing argument to support the accuracy of the 90Sr separation methods, is also offered.
Disclosure statement: No potential conflict of interest was reported by the authors.
Funding: This work was supported by the Romanian Institute for Nuclear Research under Grant [number 3936].
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Articles in the same Issue
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- Separation and quantification of 90Sr from ion-exchange resin radioactive waste: methods and techniques of analysis
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Articles in the same Issue
- 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
