PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

ACTUAL ASPECTS OF STUDIES ON THERMOHYDRAULIC PROCESSES IN FAST NEUTRON REACTORS WITH LIQUID METAL COOLING

EDN: VMHSSE

Authors & Affiliations

Sorokin A.P., Kuzina Yu.A., Delnov V.N., Denisova N.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Sorokin A.P. – Chief Researcher, Dr. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, 249033. Tel.: +7 (484) 399-84-47; e-mail:&This email address is being protected from spambots. You need JavaScript enabled to view it.
Kuzina Yu.A. – Head of Department of Nuclear Power Engineering, Cand. Sci. (Tech.).
Delnov V.N. – Head of Department, Dr. Sci. (Tech.).
Denisova N.A. – Leading Researcherg.

Abstract

The results of studies of thermal-hydraulic processes are presented to justify the characteristics and safety of sodium-cooled fast neutron reactors for a wide range of problems, including hydrodynamics and heat transfer in the channels and fuel assemblies of the core fuel rods, including under conditions of fuel bundle shaping during the campaign and blockage of part of the flow section of fuel assemblies, intravessel circulation and heat exchange of stratified coolant in a fast neutron reactor with an integral layout of equipment in the nominal regimes with forced convection and natural convection of the coolant (emergency cooldown), in heat exchangers and steam generators of fast reactors. The results of experimental studies of the features of the hydrodynamics of the flow parts of the collector systems of heat exchangers and reactors of nuclear power plants, as well as collector systems of a cylindrical type, are presented. Regularities of hydrodynamics of reservoir systems, which are the subject of scientific discoveries, are analyzed. The results of experimental studies and numerical modeling of boiling processes of liquid metals in core fuel element assemblies in emergency modes, solving the problem of passive (self-regulating) shutdown of fast reactors are analyzed.

Keywords
fast reactor, sodium, thermal hydraulics, safety, emergency modes, experiment, numerical modeling, core, reactor tank, turbulent transfer, stratification, boiling of alkali metals

Article Text (PDF, in Russian)

References

UDC 536.24:621.039.534.6

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 2, 2:15