A mathematical model for the thermal-hydraulic analysis of nuclear power plants

The adequate dynamic models are developed for the thermal-hydraulic analysis of nuclear power plants with their fast running capacity on a personal computer. The dynamic models are formulated for the primary loop systems, coupling of reactor kinetics with the feedback reactivity, and the U-tube steam generator used in most pressurized water reactors. The main work is intended to demonstrate the great capability of the dynamic models to efficiently simulate operational transients in a nuclear power plant. Various perturbations of interest are simulated for the thermal-hydraulic analysis of importance in nuclear safety. Representative simulated results of the transient analysis show the expected trends in all cases. The personal computer based dynamic models provide an accurate and suitable simulation tool which can be useful for the thermal-hydraulic transient analysis of nuclear power plants.