Abstract:

Steam generator is one of the most important equipment of PWR nuclear power plant. The operating state of the steam generator is directly related to the safety of the entire nuclear power plant, so the modeling and simulation of steam generator is of great significance for the development of nuclear industry. This paper focused on the semi-physical simulation of PWR u-tube steam generator. By analyzing the structural characteristics and operation principle of the U-shaped steam generator, the steam generator was modeled by the modular modeling method, and the simulation data was stored in the control system. In LabVIEW software, the simulation model of steam generator in PWR nuclear power plant was established based on the mathematical model in divided control parts. The Modbus protocol was used to realize the communication between the software simulation in PC and UW500 distributed system for collecting important simulated data. The semi-physical simulation of steam generator correctly simulated the operation of steam generator, showed the change of thermal parameters in the first and second circuits of steam generator, and stored the records in the distributed system. These results proved that the semi-physical simulation model could be used not only for test research in different working conditions, but also as a teaching demonstration for nuclear power research.

Key words: PWR, steam generator, LabVIEW, Modbus, UW500 distributed system, thermal parameter