Authors & Affiliations

Kuzina Ju.A., Sorokin A.P.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Kuzina Ju.A. – Deputy General Director — Director of the Department of Thermal Physics, Cand. Sci. (Techn.), A.I. Leypunsky Institute for Physics and Power Engineering.
Sorokin A.P. – Chief Researcher, Dr. Sci. (Techn.), A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7(484) 399-86-63; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..

Abstract

As a result sixty years of experience in the development of alkaline liquid metals - sodium, eutectic alloys of sodium-potassium, lithium, cesium, the scientific bases of their application in nuclear power were created, the thermohydraulic parameters and highly efficient technological processes were substantiated, devices and systems were developed and implemented that ensured the successful operation of fundamentally new NPPs. The main areas of research were: thermal hydraulics, mechanisms of turbulent heat exchange, boiling and condensation of liquid metals, physical chemistry and liquid metal coolant technology, thermophysical properties of materials of the reactor, coolants, analysis and generalization of thermophysical data, bases of the experimental data, heat pipes, thermophysics of thermionic converters, high-temperature space nuclear power units and thermonuclear installations. The results investigations of hydrodynamics and heat transfer in channels of complex shape were studied, both under normal operating conditions and deformation of a fuel cell grid. The justified reduction of collector hydraulic irregularities in reactors, heat exchangers and steam generators. A channel-by-channel method of thermal-hydraulic calculation of fuel assemblies of the core of fast reactors for nominal and non-nominal operating regimes was developed. A theory of anisotropic porous body has been developed as applied to calculations of complex flows in reactors, heat exchangers and steam generator. Experimental investigations of the circulation and heat transfer in the reactor tank during forced circulation, in transitional and accident regimes with natural circulation showed a stratification and temperature pulsations in the upper mixing chamber and other regimes of the reactor installation. The boiling processes in a large volume, tubes and bundles of rods, the condensation of liquid metals, the occurrence of accident processes during sodium leaks in steam generators and sodium circuits have been experimentally investigated. The tasks of further research are formulated.

Keywords
alkaline liquid metals, fast reactors, experiment, numerical codes, velocity, pressure, temperature, databases, thermohydraulics, physical chemistry, safety, core, reactor vessel, steam generator, emergency situation

Article Text (PDF, in Russian)

References

UDC 536.24+621.039.553.34

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2019, issue 3, 3:19