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Feasibility study of 233Pa and 233U determination in neutron irradiated thorium for future applications in thorium–uranium nuclear fuel cycle

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Abstract

With regard to the use of thorium fuel for future nuclear energy production, two methods of 233U assay were studied in neutron irradiated thorium and in a mixture of thorium and uranium. The former was based on gamma-spectrometry determination of the 233Pa radionuclide, a precursor of 233U. The latter was direct determination of 233U by neutron activation analysis with counting of delayed neutrons. The mass of 233U determined by both methods is compared with that calculated using Maple9.5 software package.

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Acknowledgments

This work was supported by Nuclear Research Institute Řež, plc. and project IRP AVOZ 10480505 of the Academy of Sciences of the Czech Republic.

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Authors and Affiliations

  1. Nuclear Research Institute Řež, plc, 250 68, Husinec-Řež 130, Czech Republic

    D. Baldová, L. Viererbl & J. Uhlíř

  2. Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Břehová 7, 115 19, Prague 1, Czech Republic

    D. Baldová

  3. Nuclear Physics Institute AS CR, 250 68, Husinec-Řež 130, Czech Republic

    J. Kučera

  4. Research Centre Řež, Ltd, 250 68, Husinec-Řež 130, Czech Republic

    J. Kučera & L. Viererbl

  5. Brno University of Technology, Faculty of Electrical Engineering and Communication Technická 3058/10, 61600, Brno, Czech Republic

    R. Škoda

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  1. D. Baldová
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  2. R. Škoda
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  3. J. Kučera
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  4. L. Viererbl
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Correspondence to D. Baldová.

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Baldová, D., Škoda, R., Kučera, J. et al. Feasibility study of 233Pa and 233U determination in neutron irradiated thorium for future applications in thorium–uranium nuclear fuel cycle. J Radioanal Nucl Chem 288, 37–42 (2011). https://doi.org/10.1007/s10967-010-0862-4

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  • DOI: https://doi.org/10.1007/s10967-010-0862-4

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