Abstract
Abstract The Secondary Circuit Passive Residual Heat Removal System (PRHRS) is designed for advanced nuclear power system. A research on thermal hydraulic characteristics of two-phase natural circulation process for secondary circuit PRHRS has been carried out using the RELAP5 code. For this, the natural circulation steam generator (SG) and the PRHRS are modeled. Five thermal boundary conditions are set to verify the function of PRHRS. The phenomenon of flow instability in the two-phase natural circulation process is of great significance for system operation, as well as the performance of SG and condenser. Therefore, the focus is on the natural circulation flowrate oscillation of steam and condensed water. The mixed water level difference between descending pipe of PRHRS and secondary side of natural circulation SG is found to be the meaningful parameter to characterize the flow instability of natural circulation. The comparative analysis is also performed by considering the effects of height between the SG and condenser, as well as system resistance, which can provide support for PRHRS design and optimization.
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