Abstract
89Sr was produced using the 89Y(n, p) 89Sr reaction by irradiating yttria target in the fast breeder test reactor (FBTR). An analytical scale procedure was standardized for the removal of the bulk target yttrium by solvent extraction using the tri-n-butyl phosphate (TBP). The final purification of 89Sr source was carried out by ion exchange chromatography. However, extraction chromatography is preferred to solvent extraction due to its low waste generation and ease of operation. This paper reports the separation of Sr from bulk Y and other radioactive impurities produced during irradiation by extraction chromatography using TBP coated XAD-4 resin. Initially the separation procedure was standardized using 85Sr and 88Y tracers. The 89Sr in the dissolver solution of the irradiated yttria target was separated under the same standardized conditions. The study established the separation of Sr from Y in the dissolver solution of the irradiated target yttria by the TBP coated XAD-4 column. However the evaluation of the column after every use for about three separation studies exhibited the reduction in its breakthrough capacity for yttrium.
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Abbreviations
- D:
-
Distribution coefficient
- Co:
-
Initial activity in solution
- C:
-
Final activity in solution
- V:
-
Volume of the solution
References
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Saha, D., Senthil Vadivu, E., Kumar, R. et al. Separation of bulk Y from 89Y(n,p) produced 89Sr by extraction chromatography using TBP coated XAD-4 resin. J Radioanal Nucl Chem 298, 1309–1314 (2013). https://doi.org/10.1007/s10967-013-2514-y
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DOI: https://doi.org/10.1007/s10967-013-2514-y