Abstract
Radiochemical-based analyses have been used for the characterization of radioactive waste. Nevertheless, the determination of alpha, beta and gamma emitters by radiochemical analysis of spent cartridge filters from a swimming-pool type reactor has not been previously addressed. This work aims at identifying and quantifying the radionuclides present in this waste, including the difficult to measure radionuclides. The distribution of the radionuclides in the filter was investigated by the determination of gamma-emitting nuclides and the z-score of the measured activity concentrations. The results indicated that all the filters are homogeneous, meeting the homogeneity criteria recommended by the International Atomic Energy Agency.
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Acknowledgements
The authors would like to thank the National Nuclear Energy Commission/Nuclear and Energy Research Institute (IPEN-CNEN/SP) for an institutional Grant. The authors also thank: Laboratório de Poços de Caldas—LAPOC—CNEN for allowing its use during some steps of the project; Dr. Marycel E. B. Cotrim and the Laboratório de Análises Química e Ambiental (LAQA) of the Centro de Química e Meio Ambiente (CQMA) for kindly perform the nickel analyzes; and Dr. Marina F. Koskinas and the Laboratório de Metrologia Nuclear (LMN) of the Centro do Reator de Pesquisas (CRPq) for the preparation of the standard solutions.
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Geraldo, B., de Araujo, L.G., Taddei, M.H.T. et al. Radiochemical characterization of spent filter cartridges from the primary circuit of a research reactor. J Radioanal Nucl Chem 322, 1941–1951 (2019). https://doi.org/10.1007/s10967-019-06864-4
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DOI: https://doi.org/10.1007/s10967-019-06864-4