Abstract
Исследование режима с малой течью в первом контуре ВВЭР-1000
Highlights
Modes with violation of the reactor facility cooling conditions in the VVER reactor primary circuit have been simulated using the TRAC PD2 and Open FOAM thermohydraulic codes [1 – 3] based on energy and mass conservation equations for a three dimensional unsteady flow of a two phase mixture
Coupled simulation of the dynamics of neutronic and thermohydraulic processes [1 – 8] aims to improve the qualitative understanding and the quantitative notion of their effects on safety. Studying these modes using the above thermohydraulic codes makes it possible to analyze the course of transients and certain emergency processes without using the industrial testing method, this providing the basis for solving the problems of ensuring the reliability, operational safety and efficiency of nuclear power plants
Thermohydraulic calculations are an essential component of most engineering and technological development works in nuclear power
Summary
Modes with violation of the reactor facility cooling conditions in the VVER reactor primary circuit have been simulated using the TRAC PD2 and Open FOAM thermohydraulic codes [1 – 3] based on energy and mass conservation equations for a three dimensional unsteady flow of a two phase mixture.
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