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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

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

Kuzina Yu.A. – Director of Nuclear Energetic Department, Cand. Sci. (Tech.).
Sorokin A.P. – Chief Researcher, Dr. Sci. (Tech.). Contacts: 1, Bondarenko sq., 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..
Denisova N.A. – Lead Engineer.

Abstract

Significant non-uniformities in the coolant temperature field associated with high heating of the liquid metal coolant (150–200 °C) and a levelling effect of inter-channel mixing on the velocity and temperature fields of the coolant due to flow swirling by spaced spiral wire wrap on fuel rods are the most characteristic features of thermal hydraulics in fuel assemblies (FA) of fast reactor core, which have a decisive effect on the formation of velocity and temperature fields in fuel assemblies in all operating conditions. The paper presents the results of complex experimental and computational studies of the physics, hydrodynamic characteristics and heat transfer in fuel assemblies with spaced spiral wire wrap on fuel rods obtained at the IPPE JSC: velocity and temperature fields of the coolant, inter-channel mixing of the coolant, hydraulic resistance of the fuel assemblies. A high intensity of inter-channel convective transfer of mass, momentum and energy in fuel assemblies due to the flow swirling by wire wrap of various types is shown. Calculation models of the inter-channel heat transfer and recommendations for calculating of the heat transfer characteristics and hydraulic resistance of fuel bundles with spaced wire wrap are presented. The results of computational studies by using MIF-2 code developed at the IPPE JSC for numerical simulation of hydrodynamics and heat transfer in fast reactor fuel assemblies with spaced spiral wire wrap on fuel rods and the comparison with the results of independent experiments and calculations on foreign codes are presented.

Keywords
hydrodynamics, heat transfer, fast reactors, core, assembly of rods, swirling flow, experiment, design codes, velocity, shear stress, temperature, interchannel exchange, convective exchange, turbulent exchange, hydraulic resistance

Article Text (PDF, in Russian)

References

UDC 536.24+621.039.553.34

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, issue 1, 1:17