Abstract
89Sr was produced via 89Y(n, p) 89Sr using yttria as target in Fast Breeder Test Reactor (FBTR), Kalpakkam, India. A radiochemical procedure has been developed for the separation of bulk yttrium using TBP by solvent extraction followed by purification of 89Sr source by ion exchange chromatography using the cation exchange resin Dowex 50WX8 (100–200 mesh) and nitric acid of variable molarity as eluant. The present study establishes the purification of 89Sr source from the other radionuclidic impurities like 88Y, 65Zn, 54Mn, 60Co, 86Rb, 192Ir, 103Ru, 113Sn, 139Ce, 160Tb, 154Eu etc. produced during the irradiation of yttria by using the complexing agent tri-sodium tri-meta phosphate (SMP) in nitric acid medium instead of nitric acid alone as an eluant. The purification was achieved by using 0.1 M SMP as complexing agent which was optimized based on the distribution ratio data and final elution of Sr fraction was obtained in nitric acid medium. This resulted into a faster purification of 89Sr source in a smaller volume of eluant. Purity of Sr source from the cross contamination of the complexing agent SMP was also ensured.
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Acknowledgments
We gratefully acknowledge the operational personnel of KAMINI reactor and FBTR who helped in the sample irradiation for the above experiments and the Irradiated Fuel Studies Section of Fuel Chemistry Division, IGCAR who helped in the experiments in hot cell facility.
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Ashok Kumar, G.V.S., Vithya, J., Siva Kumar, B. et al. Purification of 89Sr source obtained from 89Y(n, p) 89Sr by ion-exchange chromatography using tri-sodium tri-meta phosphate (SMP) as eluant. J Radioanal Nucl Chem 302, 803–808 (2014). https://doi.org/10.1007/s10967-014-3253-4
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DOI: https://doi.org/10.1007/s10967-014-3253-4