Izvestiya vuzov. Yadernaya Energetika

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

A New Circuit Solution to Minimize the Consequences of the Failure of the Feedwater Cooldown Line of the BREST-OD-300

6/30/2025 2025 - #02 Modelling processes at nuclear facilities

Popov A.V. Kulakov E.N. Danilova D.R. Lisyanskii A.S. Svyatkin F.A. Kiriyenko S.O. Bubenshikov E.V. Pavlova I.V. Khodakovsky V.V. Chigarev V.N.

DOI: https://doi.org/10.26583/npe.2025.2.13

UDC: 621.311.25.621.039

During the design of the secondary circuit for a nuclear power plant with the BREST-OD-300, engineers and designers faced specific challenges related to the properties of the lead coolant. The key issue was its high crystallization temperature, which necessitated fundamentally new approaches to the thermal circuit design of the power unit. Particular attention was paid to developing the feedwater heating system, as its parameters and configuration directly affect the thermal balance and operational stability of the reactor plant. Throughout the design process, the configuration of this system underwent multiple revisions, reflecting the complexity of achieving optimal technical solutions while meeting stringent reliability and safety requirements. Every modification to the feedwater heating system design requires comprehensive analysis of its impact on all key components of the power unit, including both the reactor and turbine circuits. Engineers employed an Integral Computational Mathematical Model (ICMM) to evaluate system performance in normal and emergency operating modes, incorporating interconnections between all technological processes. This approach not only helps identify potential issues at early design stages but also optimizes equipment operating parameters. This approach achieves significant improvements in the power unit’s economic efficiency while simultaneously meeting all reliability and safety requirements. The research placed special emphasis on analyzing accident scenarios, particularly feedwater cooldown line failure. Engineers applied mathematical modeling to pinpoint critical parameters and design failure-mitigation solutions. These included upgrades to backup heating systems and optimization of control algorithms. Thus, this work highlights the necessity of employing modern modeling methods when developing innovative nuclear reactors. Such approaches enable advance development of technical solutions to ensure safe and efficient operation of these advanced power units.

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NPP BREST-OD-300 Integral Compulation Mathematical Model Liquid Metal Coolant Lead Direct-Contact Feedwater Heater (DCFH) FHTP (Feed Hydroturbine Pump)

Link for citing the article: Popov A.V., Kulakov E.N., Danilova D.R., Lisyanskii A.S., Svyatkin F.A., Kiriyenko S.O., Bubenshikov E.V., Pavlova I.V., Khodakovsky V.V., Chigarev V.N. A New Circuit Solution to Minimize the Consequences of the Failure of the Feedwater Cooldown Line of the BREST-OD-300. Izvestiya vuzov. Yadernaya Energetika. 2025, no. 2, pp. 153-166; DOI: https://doi.org/10.26583/npe.2025.2.13 (in Russian).

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