Abstract
Modes with violation of the reactor plant cooling conditions on the primary circuit side of a VVER reactor were simulated using the TRAC-PD2 and Open FOAM thermohydraulic codes (TRAC-PD2 1981, OpenFOAM User Guide Version 1.6. 2009, OpenFOAM Programmer’s Guide Version 1.6. 2009) based on energy and mass conservation equations for the three-dimensional unsteady flow of a two-phase mixture. Coupled simulation of the dynamics of neutronic and thermohydraulic processes (TRAC-PD2 1981, OpenFOAM User Guide Version 1.6. 2009, OpenFOAM Programmer’s Guide Version 1.6. 2009, Bolshagin et al. 2009, Galanin 1971, Weinberg and Wigner 1961, Ovchinnikov and Semenov 1988, Report LA-UR-03-1987) aims to improve the qualitative understanding and the quantitative presentation of their effects on safety. Investigating 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. A modern nuclear reactor is a complex system studying and calculating which requires more than the use of simple theoretical models. Thermohydraulic calculations are an essential part of most engineering and technological development works in nuclear power. Since, in conditions of an NPP, no technologically conventional way can be used to verify and update the results and findings of an a priori analysis on the basis of commercial tests, investigations based on codes are used in some cases as the tools to study and predict the parameters of thermohydraulic processes in the reactor’s circulation circuit. The main purpose of the study is to calculate and investigate, based on codes, modes with violation of the reactor plant cooling conditions on the primary circuit side of a VVER reactor in order to determine if calculated parameters conform to the acceptance criteria established by regulatory documents.
Highlights
Research ArticleInvestigation of the small break conditions in the primary circuit of a VVER-1000 reactor*
Safe operation of a reactor plant requires accurate and timely information on the parameters of its status.The primary and the secondary circuits of an NPP with the VVER-1000 reactor are interconnected, and a variation in the primary circuit parameters may lead to an anticipated operational occurrence, in particular, to the reactor cooling and a disturbance in the secondary circuit with further development of malfunctions capable to result in an accident
– all reactor coolant pumps (RCP); – the secondary circuit’s main and auxiliary feedwater systems; – the primary circuit’s makeup and blowdown system; – high-speed dump valves with discharge to atmosphere (HSDV-A); – the pressurizer system power supply Generation of the emergency protection (EP) actuation signal Control members start to move Start of diesel generators (DG) and their stepped loading Closure of the turbine generator stop valves HSDV-A opening Start of the emergency boron injection and emergency cooldown pumps HSDV-A closure Start of boric solution supply to pipelines of loops 1, 4 by emergency injection pumps
Summary
Investigation of the small break conditions in the primary circuit of a VVER-1000 reactor*.
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