Distributed parameter modeling for the steam generator in the nuclear power plant

Abstract

Steam generator is an important equipment in nuclear power plants. This paper investigates the dynamics and heat transfer process in the vertical U-tube natural circulation steam generator. The steam generator under study is divided into four regions, i.e., the hot leg, the cold leg, the steam separator and the saturated steam chamber. Correspondingly, the mass, momentum and energy conservation equations are derived with distributed parameter modeling approach. The model system is validated with the history operation data from a Chinese nuclear power plant. The calculated thermodynamic properties of the saturated steam at the outlet of the steam generator are found to agree well with the measured values, which indirectly validates accuracy of the model system. Model-based dynamic simulation software for the steam generator is developed with which the heat transfer coefficient distribution, the pressure distribution, the temperature distribution, and the speed distribution of the working medium are obtained in real time.