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Radiation Safety Validation of a BREST-OD-300 Installation

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Atomic Energy Aims and scope

The methodology and assessment of the radiation safety of a power unit with a BREST-OD300 reactor are presented. The method of calculation is described for the considered radionuclide mass transfer zones: fuel, gas volume of a fuel rod, lead coolant, gas circuit, central hall, and volume beneath a sealed enclosure. The radiation consequences of working under normal operating conditions as well as during design-basis and beyond-design-basis accidents are analyzed.

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Authors and Affiliations

  1. NIKIET, Moscow, Russia

    N. E. Dubenkov, A. V. Proukhin, A. A. Bazhanov, V. P. Vasyukhno, V. V. Lemekhov, A. V. Moiseev & G. A. Khacheresov

  2. IBRAE RAS, Moscow, Russia

    A. A. Kiselev & S. N. Krasnoperov

Authors
  1. N. E. Dubenkov
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  2. A. V. Proukhin
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  3. A. A. Bazhanov
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  4. V. P. Vasyukhno
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  5. V. V. Lemekhov
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  6. A. V. Moiseev
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  7. G. A. Khacheresov
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  8. A. A. Kiselev
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  9. S. N. Krasnoperov
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Corresponding author

Correspondence to N. E. Dubenkov.

Additional information

Translated from Atomnaya Énergiya, Vol. 130, No. 4, pp. 223–228, April, 2021.

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Dubenkov, N.E., Proukhin, A.V., Bazhanov, A.A. et al. Radiation Safety Validation of a BREST-OD-300 Installation. At Energy 130, 238–243 (2021). https://doi.org/10.1007/s10512-021-00802-y

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  • DOI: https://doi.org/10.1007/s10512-021-00802-y

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