Research On Modeling Conventional Island Of Lingao Phase Ⅱ Nuclear Power Plant Thermal-Hydraulic System

Safety analysis is an important aspect of Nuclear power plant study, as well as an important tool to verify nuclear power plant thermal-hydraulic system model. Traditional nuclear power plant safety analysis was confined to the study of nuclear island, using boundary conditions to simulate the secondary loop, had significant limitations. With the development of nuclear power plant safety analysis, the scope of its research gradually expanded to the entire nuclear power system which includes conventional island. Therefore, the establishment of a complete nuclear power plant nuclear island and conventional island model, especially a complete model of conventional island, is very significant for safety analysis of nuclear power plant under various conditions.Conventional Island thermal-hydraulic system model covered steam turbine system, bypass system, separator reheater system, condenser system, condensate pumps and the main water supply system, low pressure and high-pressure feedwater heater system, extraction hydrophobically system, feedwater heater bypass systemand the related control systems. In this paper, RELAP5 procedures is adopted to model the conventional island thermal-hydraulic system of Ling'ao phase II nuclear power plant, and making a verification of a steady-state and a series of transient operating conditions. Validated analysis shows that the results of steady-state model coincide with the practical data; transient trends are the same as the actual situation of nuclear power plants, which verifies the correctness and reliability of the model.Studies have shown that the Conventional Island thermal-hydraulic system model which has been established in this paper is reliable; it provides an effective tool for engineers to carry out transient analysis of nuclear power plant.