EXPERIMENTAL RESEARCHES OF TEMPERATURE FIELDS AND COOLANT FLOW STRUCTURES IN ELEMENTS OF PRIMARY CONTOUR ON FAST REACTOR MODEL AT V-200 FACILITY AT TRANSITION TOCOOLING BY NATURAL CIRCULATION

ISSUES

Authors & Affiliations

Opanasenko A.N., Sorokin A.P., Zarugin D.G., Denisova N.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Sorokin A.P. – Deputy Director of Safety Department, Dr. Sci. (Tech.), A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, sq. Bondarenko, Obninsk, Kaluga reg., Russia, 249033, Tel.: (484) 399-84-47, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.
Opanasenko A.N. - leading researcher, Cand. Sci. (Tech), A.I. Leypunsky Institute for Physics and Power Engineering.
Zaryugin D.G. – deputy director of Institute for Nuclear reactors and Thermal Physics, Cand. Sci. (Tech.), 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.

Abstract

The results of experimental studies of temperature fields and the flow structure of non-isothermal coolant in the elements of fast reactor primary contour on an integral three-loop water model are presented and analyzed. Objective: obtaining experimental data to justify the design solution for Decay Heat Removal System, the data for verification ofcomputer codes, the study features of thermal hydraulics in non-isothermal flow of coolant, to develop of recommendationson intensifying the mixing of non-isothermal coolant. Studies conducted in various modes: forced circulation, the transitional regime from forced circulation to natural, steadystate cool down by natural circulation, including modes with partial shutdown of equipment primary and secondary circuits. The measurement results of the temperature fields shown on a stable temperature stratification of coolant: in the peripheral region of the upper reactor chamber above the sidescreen, cold and pressure chamber, elevator shield, the cooling system of the reactor vessel,on outlet of the intermediate (IHX), and autonomous (AHX) heat exchangers in various modes. The large gradients and temperature fluctuations at the interface of stratified and recycling zones influencing on resort of reactor equipment were registered.

Keywords
fast reactor, thermal hydraulics, primary contour, integrated model, experimental researches, transients, decay heat removal, natural convection, coolant stratification, temperature pulsation

Article Text (PDF, in Russian)

References

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UDC 621.039.516.25:621.039.526

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2016, issue 5, 5:7

BROND-3.1

ISSUES

EXPERIMENTAL RESEARCHES OF TEMPERATURE FIELDS AND COOLANT FLOW STRUCTURES IN ELEMENTS OF PRIMARY CONTOUR ON FAST REACTOR MODEL AT V-200 FACILITY AT TRANSITION TOCOOLING BY NATURAL CIRCULATION