Authors & Affiliations

Opanasenko A.N.1, Sorokin A.P.1, Trufanov A.A.1, Denisova N.A.1, Razuvanov N.G.3, Sviridov Eu.V.2, Belyaev I.A.3
1A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2Moscow Power Engineering Institute, Moscow, Russia
3Joint Institute of High Temperatures of Russian Academy of Science, Moscow, Russia

Opanasenko A.N. – Cand. Sci. (Tech.), Leading Researcher of Safety Department, A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: (484)399-89-30; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Sorokin A.P. – Dr. Sci. (Tech.), Deputy Director of Safety Department, A.I. Leypunsky Institute for Physics and Power Engineering.
Trufanov A.A. – Deputy Director General, Director of Safety Department, A.I. Leypunsky Institute for Physics and Power Engineering.
Denisova N.A. – Leading Engineer of Safety Department, A.I. Leypunsky Institute for Physics and Power Engineering.
Razuvanov N.G. – Dr. Sci. (Tech.), Leading Researcher, Joint Institute of High Temperatures of Russian Academy of Science.
Sviridov Eu.V. – Cand. Sci. (Tech.), Docent, Moscow Power Engineering Institute.
Belyaev I.A. – Cand. Sci. (Tech.), Head of the laboratory, Joint Institute of High Temperatures of Russian Academy of Science.

Abstract

The results of experimental studies of the structure of the movement, non-isothermal temperature fields and coolant velocity in the water model in different regimes in relation to the various types of nuclear power. Research carried out on transparent models of reactor coolant system and for drop VVER channel sector model of the upper chamber of a fast reactor and water three-loop model of a fast reactor with integral equipment arrangement in the first circuit. Measurements of local velocities height and radius of the upper mixing chamber in a plane in the direction of the center of the core to the intermediate heat exchanger in the reactor on fast neutrons model for the first time possible to obtain three-dimensional picture of the velocity field in the volume of the upper chamber in a forced circulation of the coolant and reactor emergency cooling by natural convection. As a result, the measurement of temperature and velocity fields using specially designed measuring instruments identified areas with a stable temperature stratification with large gradients and fluctuations of temperature at the interface of stratified and recirculation zones. The results obtained enable us to judge about the amplitude and frequency characteristics of the temperature fluctuations in these potentially dangerous areas for different modes of operation of the reactors. The data obtained can be used to verify the thermal-hydraulic codes used to justify the design characteristics and safety of nuclear reactors.

Keywords
experimental studies, a fast reactor, the reactor tank, experimental water model, the integrated arrangement, the upper chamber, thermal hydraulics, local characteristics, velocity, temperature stratification of the coolant, stationary processes, transients, emergency cooling, natural convection, the temperature non-uniformity, ripple, verification codes

Article Text (PDF, in Russian)

References

UDC 621.039.516.25:621.039.526

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2016, issue 4, 4:24