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Quantification of 241Pu in aerosols released from nuclear power plants

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Abstract

A radiochemical method is described for the determination of 241Pu activity in gaseous effluents released to the environment from nuclear power plants. For the analysis of samples 236Pu isotope is used as an analytical tracer. A correlation factor between the gross alpha and the 236Pu activity measured by alpha-spectrometry was obtained and applied to the gross alpha, obtained by liquid scintillation counting (LSC). The minimum detectable activity (MDA) was 0.12 Bq/filter, for LSC efficiency of 25% and a recovery of 52%. The final calculation of the total propagated uncertainty on a real sample is presented.

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Authors and Affiliations

  1. Nuclear Regulatory Authority, Prebistero J. Gonzales y Aragon 15, B1802, Ezeiza, Buenos Aires, Argentina

    J. M. Diodati

  2. Radiochemistry Unit, National Commission of Atomic Energy, Prebistero J. Gonzales y Aragon 15, B1802, Ezeiza, Buenos Aires, Argentina

    M. L. Cerchietti

Authors
  1. J. M. Diodati
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  2. M. L. Cerchietti
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Diodati, J.M., Cerchietti, M.L. Quantification of 241Pu in aerosols released from nuclear power plants. J Radioanal Nucl Chem 274, 9–13 (2007). https://doi.org/10.1007/s10967-006-6881-5

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  • DOI: https://doi.org/10.1007/s10967-006-6881-5

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