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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

A radiochemical separation and purification of 99 Tc 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 Quant...

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Bibliographic Details
Published in:Journal of radioanalytical and nuclear chemistry 2016-02, Vol.307 (2), p.1453-1458
Main Authors: Temba, Eliane S. C., Reis, Aluísio S., Kastner, Geraldo F., Monteiro, Roberto P. G., Moreira, Rubens M.
Format: Article
Language:English
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Summary:A radiochemical separation and purification of 99 Tc 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 .
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-015-4359-z