Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Providing Scientific and Technical Support for Operation of the BN-600 Power Unit

9/10/2025 2025 - #03 Nuclear power plants

Bel’tyukov A.I. Govorov P.P. Karpenko A.I. Nosov Yu.V. Oshkanov N.N. Tuchkov A.M. Shcheklein S.E.

DOI: https://doi.org/10.26583/npe.2025.3.04

UDC: 621.039.526

Successful operation of the unique BN-600 power unit with a high-power fast sodium reactor with an integral layout of the primary circuit for more than 40 years became possible due to the high quality of the design, construction and installation works, qualification of the operating personnel, as well as continuous, long-term scientific and technical support of operation by the research department of the Beloyarsk NPP and scientific and design organizations of Rosatom. In the process of mastering the capacity and subsequent operation, physical and thermal physical features were discovered, the consideration of which was impossible at small-scale installations and experimental stands. The studies concerned all circuits and units of equipment and operating modes of the power unit.

In the primary circuit of the integral sodium reactor BN-600, studies of the sector (loop) coolant flow were carried out. The main quantitative relationships between changes in the thermal-hydraulic parameters of the circuits and the values of the maximum permissible difference in the rotation speedsof the main circulation pumps of the 1st circuit (MCP-1) are determined. In the reactor cooldown modes, the rates of heat removal from the core for various combinations of operating equipment are investigated. To determine defective fuel assemblies (FA) by fuel, a technique for searching for leaky FAs is proposed based on the developed method of relative weighing of compensating rods (CR). The dependences of the interference coefficient of the CR system on the position of the CR rods in the zone are determined. Based on the results of pilot production of cobalt-60 radionuclide in the reactor, the possibility of producing isotope products on an industrial scale is shown. The main thermal-hydraulic characteristics of the once-through sectional steam generators (SG) ‘sodium-water’ PGN-200M for each loop are obtained, taking into account the number of disconnected modules. The study of the SG temperature modes, the investigation of the maximum heat flows in the evaporators and the removal of moisture from the evaporator made it possible to establish the permissible (maximum power) capabilities of the SG, which ensures the stability of the BN-600 unit against failures of individual equipment. To ensure normal thermal efficiency of the SG due to the deterioration of heat exchange when the protective gas passes through the circulation circuit, the gas capture boundary from the sodium buffer tank (SBT) was determined depending on the operating parameters of the circuit. Optimum durations of the SG inter-wash periods were established. Depending on the operating time, with the accumulation of significant deposits in the SG, an increase in the hydrodynamic instability area (HDI) was detected. Based on the results of the studies of the SG operating modes, the HDI boundaries of the steam-water flow were determined.

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sector flow model reactor power thermal hydraulics reactivity effects core control rod efficiency isotope production steam generator hydrodynamic instability

Link for citing the article: Bel’tyukov A.I., Govorov P.P., Karpenko A.I., Nosov Yu.V., Oshkanov N.N., Tuchkov A.M., Shcheklein S.E. Providing Scientific and Technical Support for Operation of the BN-600 Power Unit. Izvestiya vuzov. Yadernaya Energetika. 2025, no. 3, pp. 60-73; DOI: https://doi.org/10.26583/npe.2025.3.04 (in Russian).

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