dynamic simulation of heat transfer in cogenerative nuclear reactors

A high rate of the personal energy consumption can be maintained in the face of rapidly growing population densities only if enough energy resources are available. since fossil fuels are an unlimited supply and the petroleum sources appear to be uncertain, the search for more energy sources is more important. these reasons are adequate to direct the world to search for a new generating capacity based on nuclear power. this study considers the problem of heat transfer in nuclear reactors and studies the dynamic behavior of the pressurized water reactor (PWR) under some transient cases. A mathematical model for the westinghouse of 3411 M Wth pressurized water reactor was developed. the model consists basically of two parts, the first part is concerned with the dynamics of the primary side of the reactor which consists of the rector and its upper and lower plenums and the steam generator which is of the u-tube type. the second part is concerned with the steam side of the plant, which contains the tubine plante (a low pressure turbine and a high- pressure turbine), the moisture separator and the main feed water heater system.to study the dynamics of the reactor a model of 17 lumped parameters was used. seventeen first order differential equations were deduced from the first principles considering six groups of delayed neutrons