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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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Published in: | Atomic energy (New York, N.Y.) N.Y.), 2021-08, Vol.130 (4), p.238-243 |
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creator | 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. |
description | 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. |
doi_str_mv | 10.1007/s10512-021-00802-y |
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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 |
title | Radiation Safety Validation of a BREST-OD-300 Installation |
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