Radiation Safety Validation of a BREST-OD-300 Installation

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 s...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2021-08, Vol.130 (4), p.238-243
Main Authors: Dubenkov, N. E., Proukhin, A. V., Bazhanov, A. A., Vasyukhno, V. P., Lemekhov, V. V., Moiseev, A. V., Khacheresov, G. A., Kiselev, A. A., Krasnoperov, S. N.
Format: Article
Language:English
Subjects:
Analysis
Circuits
Energy industry
Hadrons
Heavy Ions
Mass transfer
Nitrides
Nuclear Chemistry
Nuclear Energy
Nuclear fuel elements
Nuclear fuels
Nuclear Physics
Nuclear power plants
Nuclear safety
Physics
Physics and Astronomy
Radiation
Radioisotopes
Safety and security measures
Uranium
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Description
Summary: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.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-021-00802-y