Authors & Affiliations

Blinkov V.N.1,2, Iskhakov A.S.1, Melikhov V.I.1,2, Melikhov O.I.1,2, Selkin S.S.3
1 National Research University "Moscow Power Engineering Institute", Moscow, Russia
2 Electrogorsk Research and Engineering Center on NPP Safety, Electrogorsk, Russia
3 Bauman Moscow State Technical University, Moscow, Russia

Blinkov V.N. – Professor of NPP Department, Dr. Sci. (Tech.), Scientific Supervisor, National Research University "Moscow Power Engineering Institute", Electrogorsk Research and Engineering Center on NPP Safety.
Iskhakov A.S. – graduate student, National Research University "Moscow Power Engineering Institute". Contacts: 14, Krasnokazarmennaya st., Moscow, Russia,111250. Tel.: +7(915)221-75-81; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Melikhov V.I. – Professor, Dr. Sci. (Tech.), National Research University "Moscow Power Engineering Institute", Electrogorsk Research and Engineering Center on NPP Safety.
Melikhov O.I. – Deputy Director, Dr. Sci. (Phys.-Math.), National Research University "Moscow Power Engineering Institute", Electrogorsk Research and Engineering Center on NPP Safety.
Selkin S.S. – student, Bauman Moscow State Technical University.

Abstract

One of the key objectives on the path to realizing prospective projects of fast neutron reactors with heavy liquid metal coolant (HLMC – lead, eutectic lead-bismuth) in the near future is the safety assessment in primary-to-secondary leak accidents in steam generators. Despite the absence of any exo-thermic chemical reactions between HLMC and water (in contrast to the violent exothermic interaction between the sodium coolant and water), the accident under review is considered as the most dangerous and poorly studied due to the complexity of the occurring thermophysical processes.
The mathematical model description of water formations flashing and evaporation in HLMC is pre-sented in the article. The model is based on the thermodynamic equilibrium of the two-phase mixture; the coolant is considered as an ideal incompressible fluid. The model allows simulating the dynamics of individual two-phase formations (a drop in a vapor bubble) or a cavern with a steam-water mixture injection into it from a defective tube. The effect of contact heat exchange between the coolant and steam-water formations is considered and it is shown that at the initial stage of the accident the effect of heat exchange is negligible and the problem can be considered in an adiabatic formulation due to the smallness of the time scales and the heat-transfer coefficient.
A brief review of experimental research devoted to the study of thermophysical processes during the outflow of water in a HLMC is performed. Time dependences of pressure and velocity in the coolant are plotted, which are compared with the results of experimental studies on the LIFUS facility.

Keywords
primary-to-secondary leak, steam generator leak, heavy liquid metal coolant, two-phase water mixture flashing and evaporation

Article Text (PDF, in Russian)

References

UDC 532.5.031

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2018, issue 2, 2:1