No abstract available

No abstract available

[en] BREST-OD-300, an innovative inherent safety fast reactor, is being developed as a pilot and demonstration prototype for the basic commercial reactor facilities of future nuclear power with a closed nuclear fuel cycle. Coolant in the reactor facility is lead, the layout of the primary circuit is integral, the reactor vessel material is multilayer metal concrete. The reactor core design uses mixed uranium-plutonium nitride as the fuel, and the fuel elements are contained in shroudless fuel assemblies (FA). Small reactivity margin, excluding prompt-neutron runaway is provided in the core. Decisions are based on a computational and experimental justification. To confirm the fuel serviceability, radiation tests of fuel elements are conducted in fast reactors. Full-scale fuel-free mockups of FA are tested. Tests have been conducted of the vessel elements. Experiments have confirmed the absence of a dependent break of steam generator tubes. Neutronic codes have been verified, including with the use of BFS critical assemblies. Loop facilities have been built on which studies are conducted to determine the radionuclide release from the coolant. It has been shown based on the calculation results that the probability of the core damage (without core melting) for nuclear power plants with the BREST-OD-300 reactor facility does not exceed 8.65·10^-9 1/year. (author)

No abstract available

[en] Conclusion: 1. Based on the concept of inherent safety, technical solutions have been developed. 2. The design approaches to the reactor equipment have been experimentally justified based on mockups of the equipment and its components and by means of computational justification with regard for the lead coolant effects; prototypes are being tested. 3. The reactor core design approaches have been validated by positive results of irradiation experiments, hydraulic and vibration experiments, analysis of neutronics using the certified codes. 4. The thermal-hydraulic calculations performed using CFD codes have shown that during anticipated operational occurrences with multiple failures superimposed, safe operation limits in terms of fuel and cladding temperatures are not exceeded and the localizing function of the reactor unit vessel is ensured. 5. The results of the radiation safety analysis have confirmed the implementation of target indicators, including no need for evacuation and resettlement of the public outside the site during anticipated operational occurrences with multiple failures. 6. The experiments formed the basis of the developed regulatory framework. 7. The BREST-OD-300 unit design is in the process of licensing with Rostekhnadzor.

[en] BREST-OD-300, an innovative inherent safety fast reactor, is being developed as a pilot and demonstration prototype for the basic commercial reactor facilities of future nuclear power with a closed nuclear fuel cycle. Coolant in the reactor facility is lead, the layout of the primary circuit is integral, the reactor vessel material is multilayer metal concrete. The reactor core design uses mixed uranium-plutonium nitride as the fuel, and the fuel elements are contained in shroudless fuel assemblies (FA). Small reactivity margin, excluding prompt-neutron runaway is provided in the core. Decisions are based on a computational and experimental justification. To confirm the fuel serviceability, radiation tests of fuel elements are conducted in fast reactors. Full-scale fuel-free mockups of FA are tested. Tests have been conducted of the vessel elements. Experiments have confirmed the absence of a dependent break of steam generator tubes. Neutronic codes have been verified, including with the use of BFS critical assemblies. Loop facilities have been built on which studies are conducted to determine the radionuclide release from the coolant. It has been shown based on the calculation results that the probability of the core damage (without core melting) for nuclear power plants with the BREST-OD-300 reactor facility does not exceed 8.65·10^-9 1/year. (author)