Thermophysical Studies – the Foundation for Sodium Using in Modern Fast Reactors
9/10/2025 2025 - #03 Thermal physics and thermal hydraulics
Sorokin A.P. Kuzina Yu.A. Alekseev V.V. Denisova N.A.
https://doi.org/10.26583/npe.2025.3.08
UDC: 536.24+621.039.553.34
As a result of a large complex of experimental and theoretical studies of sodium coolant, a scientific substantiation of highly efficient technologies and thermal-hydraulic parameters of modern installations with fast neutron reactors BN-600 and BN-800 was carried out. The paper presents and analyzes the physical and chemical processes and technology of sodium coolant: formation, mass transfer and deposition in circulation circuits of oxides and corrosion products, methods and means of purification and control of impurities in sodium coolant, as well as the results of studies on hydrodynamics and heat exchange in the core and equipment units (heat exchangers, sodium-water steam generators) of BN-600 and BN-800 reactors, flow parts of collector systems of heat exchangers and reactors, physical features and characteristics of the boiling process of liquid metal coolant in the core in emergency modes, obtained to substantiate thermal hydraulics and reactor safety.
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fast reactors sodium physical chemistry technology thermal hydraulics safety experiment calculation codes boiling core heat exchanger steam generator accident regimes
Link for citing the article: Sorokin A.P., Kuzina Yu.A., Alekseev V.V., Denisova N.A. Thermophysical Studies – the Foundation for Sodium Using in Modern Fast Reactors. Izvestiya vuzov. Yadernaya Energetika. 2025, no. 3, pp. 112-121; DOI: https://doi.org/10.26583/npe.2025.3.08 (in Russian).
