MODERN APPROACHES TO THE DEVELOPMENT OF METHODS OF NUMERICAL MODELING OF MASS AND HEAT TRANSFER PROCESSES IN FAST REACTOR FUEL ASSEMBLIES AND THEIR PRACTICAL IMPLEMENTATION

Authors & Affiliations

Sorokin A.P.¹, Sorokin G.A.², Kuzina Yu.A.¹, Denisova N.A.¹
¹ A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
² Research University “Moscow Institute of Physics and Technology”, Moscow, Russia

Sorokin A.P. – Chief Researcher, Dr. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-70-00 (add. 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.).
Denisova N.A. – Lead Engineer.
Sorokin G.A. – Associate Professor, Cand. Sci. (Tech.).

Abstract

The results of a large volume of studies of the regularities of thermal-hydraulic processes in fast reactors are accumulated in calculation programs, which are the main tool for designing reactor installations and justifying their safety. The theoretical foundations of the main methods of mathematical modeling of mass and heat exchange processes during the flow of multiphase compressible coolants in fuel rod assemblies of fast reactors are presented: fluid dynamics models, a porous body and a channel-by-channel calculation method. The main content of modern thermal-hydraulic analysis methods for reactor applications are differential equations of motion and energy of a continuous medium within the framework of a fluid dynamics model, macrotransfer of mass, momentum and energy of a porous body model and a channel-by-channel calculation model with the corresponding closing relations and boundary conditions. The most complete consideration of the influence of various factors on temperature fields in fuel assemblies (deformation, non-uniform energy release, stochastic deviations of parameters, etc.) and interchannel exchange mechanisms with ensuring high calculation accuracy is carried out in the channel-by-channel calculation method. Based on the established analogy between the macrotransfer equations within the channel-by-channel calculation model, the porous body model and the continuum equations, the class of macrotransfer equations is analyzed, the initial and boundary conditions are formulated, numerical methods for solving the system of macrotransfer equations within the channel-by-channel model and the porous body model are indicated. Numerous programs created for numerical modeling of fuel assembly characteristics for various reactor conditions are analyzed. The development of a promising direction of computational studies by fluid dynamics methods, the development and use of CFD programs for numerical modeling of thermal hydraulics, as well as the conjugation of system thermal hydraulics and three-dimensional neutron-physical programs and CFD programs for modeling the primary circuit thermal hydraulics of reactor plants for the analysis of reactor plant safety are discussed.

Keywords
fast reactors, liquid metals, core, thermal hydraulics, safety, numerical modeling, calculation methods, fluid dynamics equations, subchannel method, porous body model, calculation programs, system programs

Article Text (PDF, in Russian)

References

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UDC 536.24: 621.039.524.4: 621.039.58

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 3, 3:12

BROND-3.1

ISSUES

2025 Issue 3

MODERN APPROACHES TO THE DEVELOPMENT OF METHODS OF NUMERICAL MODELING OF MASS AND HEAT TRANSFER PROCESSES IN FAST REACTOR FUEL ASSEMBLIES AND THEIR PRACTICAL IMPLEMENTATION