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Extraction-chromatographic recovery of 90Sr from spent nuclear fuel

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Radiochemistry Aims and scope

Abstract

A procedure for recovery of 90Sr from spent nuclear fuel of the AM reactor with burn-up of 3%, stored for 1 year, is described. The procedure is based on the use of a strontium-specific solid extractant, Sr Resin. The degree of separation from radioactive and nonactive impurities allows the use of the 90Sr obtained as a raw material for high-purity 90Y.

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Authors and Affiliations

  1. Leipunskii Institute of Energy Physics, State Research Center of the Russian Federation, Obninsk Kaluga oblast, Russia

    V. V. Shapovalov, V. V. Kanygin, A. G. Naryshkin, N. A. Nerozin & E. Ya. Smetanin

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  1. V. V. Shapovalov
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  2. V. V. Kanygin
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  3. A. G. Naryshkin
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  4. N. A. Nerozin
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  5. E. Ya. Smetanin
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Additional information

Original Russian Text © V.V. Shapovalov, V.V. Kanygin, A.G. Naryshkin, N.A. Nerozin, E.Ya. Smetanin, 2006, published in Radiokhimiya, 2006, Vol. 48, No. 1, pp. 49–50.

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Shapovalov, V.V., Kanygin, V.V., Naryshkin, A.G. et al. Extraction-chromatographic recovery of 90Sr from spent nuclear fuel. Radiochemistry 48, 53–54 (2006). https://doi.org/10.1134/S1066362206010115

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  • DOI: https://doi.org/10.1134/S1066362206010115

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