Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

DOI: 10.55176/2414-1038-2020-2-104-130

Authors & Affiliations

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

Sorokin A.P.1 – Main Researcher, Dr. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 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 Ju.A.1 – Deputy Director General — Director of Nuclear Energetic Department, Cand. Sci. (Tech.).
Denisova N.A.1 – Leading Engineer, Leypunsky Institute for Physics and Power Engineering.
Sorokin G.A.2 – Associate Professor of Department of Corporate Information Systems, Cand. Sci. (Tech.).


The results of experimental and computational-theoretical studies of the transverse interchannel molecular-turbulent and convective exchange of mass, momentum and energy are presented in the framework of the channel-by-channel model of thermohydraulic calculation of fuel assemblies of fuel elements of the fast reactors core with liquid metal coolants for nominal, non-nominal and accident conditions. A complete system of inter-channel exchange coefficients is obtained for closing the system of macro-transport equations in a wide range of parameters, taking into account the fuel assemblies deformation. It was shown that transverse convective exchange in fuel assemblies with spacing by wire wrapped is caused by a deficit of static pressure in the region behind winding at the surface of the rod, and the high intensity of molecular-turbulent exchange in tight bundles is explained by the appearance of secondary flows in cells. The heat exchange between cells due to the thermal conductivity of the fuel rods is determined by the thermal modeling parameter of the fuel rods for the first harmonic. The effect of wire wrapped on the flow can be modeled by periodically changing hydraulic resistance to the transverse coolant flow. The integral model of convective inter-channel exchange in fuel assemblies with distance wire wrap is substantiated. Taking into account the centrifugal effect and calculating the interchannel exchange coefficients taking into account the local distribution of parameters allows us to clarify the thermohydraulic characteristics in the shaped bundles. For the characteristic parameters of fuel assemblies of fast reactors (Pe ≥ 50; S/d ≥ 1,1; h/d ≤ 30; ε1 < 1) the predominant is convective inter-channel exchange due to the spacing of fuel rods by wire wrapped. For highly heat-conducting fuel compositions, a significant contribution to the inter-channel heat exchange can be made by the exchange due to the thermal conductivity of the fuel elements. At a low flow rate (Pe <50), the contribution of molecular-turbulent exchange and heat exchange increases due to the thermal conductivity of the fuel rods.

fast neutron reactor, fuel rod assembly, channel-by-channel method of thermohydraulic calculation, inter-channel exchange, experiment, computational simulation, liquid metals, molecular, turbulent, convective, mass, momentum, energy, velocity, pressure, temperature, transport nonequivalence coefficient, deformation lattice, the wire wrapped

Article Text (PDF, in Russian)


UDC 621.039.526:621.039.54

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2020, issue 2, 1:11