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Separation of gram quantities of uranium from fission products by extraction chromatography

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Abstract

The separation of gram quantities of uranium from fission products has been investigated by extraction chromatography. The separation which is based on the difference in distribution coefficients between uranium and the fission products on a tributyl phosphate (TBP) resin in nitric acid medium, was carried out by means of high acidity feed and stepwise elution on a TBP chromatography column. The results show that this technique is capable to separate 5 g of uranium from a large quantity of fission products. The recovery of uranium is more than 99%. The decontamination factors of g- and b-activities were 2.1.103 and 2.3.103, respectively.

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Authors and Affiliations

  1. China Institute of Atomic Energy, P. O. Box 275(39), Beijing, 102413, P. R. China

    Yin Dongguang, Liang Yufu, Miao Zengsheng, Li Baolong, Bai Chunqi & Luo Zhifu

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  1. Yin Dongguang
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  2. Liang Yufu
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  3. Miao Zengsheng
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  4. Li Baolong
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  5. Bai Chunqi
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  6. Luo Zhifu
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Dongguang, Y., Yufu, L., Zengsheng, M. et al. Separation of gram quantities of uranium from fission products by extraction chromatography. Journal of Radioanalytical and Nuclear Chemistry 254, 629–631 (2002). https://doi.org/10.1023/A:1021675029335

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