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Separation and determination of the difficult-to-measure radionuclide 99Tc in radioactive wastes from nuclear power plants by using extraction chromatography and radiometric techniques

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Abstract

A radiochemical separation and purification of 99Tc is proposed for radioactive wastes from Brazilian nuclear power plants. The method uses anion exchange and extraction chromatography employing a TEVA resin. The radiometric determination was performed by liquid scintillation counting using a Quantulus 1220 spectrometer. Rhenium is used as a yield monitor and the chemical recovery was in the range of 70–90 %. The limit of detection, L d, obtained was 3.15 Bq L−1.

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Acknowledgments

The authors are very grateful to Eletrobrás Termonuclear for making available the samples and to Centro Nacional de Desenvolvimento Científico e Tecnológico— CNPq for the financial support.

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Authors and Affiliations

  1. Centro de Desenvolvimento da Tecnologia Nuclear – (CDTN-CNEN), Serviço de Reator e Técnicas Analiticas – (SERTA), Av. Presidente Antônio Carlos, 6627, Campus da UFMG – Pampulha, Belo Horizonte, MG, 30123-970, Brazil

    Eliane S. C. Temba, Aluísio S. Reis Jr., Geraldo F. Kastner, Roberto P. G. Monteiro & Rubens M. Moreira

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  1. Eliane S. C. Temba
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  2. Aluísio S. Reis Jr.
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  3. Geraldo F. Kastner
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  4. Roberto P. G. Monteiro
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  5. Rubens M. Moreira
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Correspondence to Eliane S. C. Temba.

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Temba, E.S.C., Reis, A.S., Kastner, G.F. et al. Separation and determination of the difficult-to-measure radionuclide 99Tc in radioactive wastes from nuclear power plants by using extraction chromatography and radiometric techniques. J Radioanal Nucl Chem 307, 1453–1458 (2016). https://doi.org/10.1007/s10967-015-4359-z

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  • DOI: https://doi.org/10.1007/s10967-015-4359-z

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