Modeling And Simulation Of The First-loop In PWR Nuclear Power Plant Based On STAR-90

This paper is divided into two parts which are reactor core and pressurizer in order to conduct modeling and simulation study. The model called typical six groups of delayed neutron is selected in order to study the core neutron flux. Meanwhile, Control rod position, fuel and moderator temperature, xenon and samarium poisoning, boron concentration effecting on the distribution of neutron flux are also considered. Non-equilibrium model of the two areas is used to study the pressurizer. Firstly, algorithm and graphic primitive definition for each module are studied based on STAR-90 simulation system. Secondly, programming with C++, algorithm storage and algorithm debugging are studied using C++ Builder5.0 software. Finally, with some disturbance curves the simulation models of reactor core and pressurizer have achieved reasonable results.