Authors & Affiliations

Iskhakov A.S.1, Melikhov V.I.1, Melikhov O.I. 2 , Rtishchev N.A. 1
1National Research University “Moscow Power Engineering Institute”, Moscow, Russia
2Electrogorsk Research and Engineering Center on NPP Safety, Electrogorsk, Russia

Iskhakov A.S. – PhD 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. – Dr. Sci. (Tech.), Professor, National Research University “Moscow Power Engineering Institute”.
Melikhov O.I. – Dr. Sci. (Phys.-Math.), Deputy Director, Electrogorsk Research and Engineering Center on NPP Safety.
Rtishchev N.A. – Cand. Sci. (Tech.), Leading Engineer, National Research University “Moscow Power Engineering Institute”.

Abstract

Steam generator tube rupture in nuclear power installations with heavy liquid metal coolants leads to the interaction of the secondary coolant (water with high thermodynamic parameters) with the primary coolant (molten lead, eutectic alloy lead-bismuth). The potential hazard at an early stage of the outflow associated with the formation and propagation of the pressure wave, which under adverse conditions can cause of the chain steam generator neighboring tubes rupture. The pressure wave caused by large pressure difference at the circuits of nuclear power installation, as well as the rapid expansion of water in consequence of sharp pressure decrease. For the analysis of these phenomena, it has been developed a model of instant energy release in the finite volume of a frictionless incompressible liquid, obtained by generalizing of the model of point source explosion to the event of a finite volume of energy release. The general conservations equations, describing fluid flow under water droplet expansion have been solved to obtain the spatial and time distribution of pressure and velocity of the fluid. It has been evaluated hydrodynamic force on the steam generator tube of BREST reactor with the help of the developed model. The value of this force is more than an order of magnitude less than the maximum design ultimate strength of the steam generator tubes.

Keywords
steam generator tube rupture, heavy liquid metal coolant, instant energy release, BREST nuclear reactor, chain tube rupture, hydrodynamic force

Article Text (PDF, in Russian)

References

UDC 532.5.031

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2016, issue 4, 4:6