Analysis of Alternative Shutdown Cooling for Chinshan Nuclear Power Plant Using CFD Simulation
The Chinshan Nuclear Power Plant (CSNPP) is a GE-designed BWR4 plant, having two identical units with rated core thermal power of 1804 MWt each unit. Several alternative shutdown cooling methods driven by natural or mixed convection has been proposed by the plant for studying the core cooling capability when the Residual Heat Removal (RHR) system is not available and the refueling tasks, such as the IVVI (In Vessel Visual Inspection) work etc., is being proceeded. One of the examples is to connect a pipe from the new spent fuel heat exchanger outlet to the reactor cavity. The design of the alternatives shall ensure that the maximum core fluid temperature is limited below the boiling temperature of water. In this study, a Computational Fluid Dynamics (CFD) model is developed to analyze the natural convection phenomena during the shutdown period. Through a series of assumption, modeling and meshing processes, a 4.0 million meshes calculation domain including the RPV, reactor cavity and spent fuel pool, are solved in this study. The analysis results show that the passive alternative shutdown cooling system can provide sufficient heat removal capability to maintain the maximum core fluid temperature below boiling temperature. The results also indicate that the alternative shutdown cooling system could be served as an appropriate alternative shutdown cooling solution for CSNPP when the RHR is inoperable.
CSNPP BWR4 RHR alternative shutdown cooling IVVI CFD
Yung-Shin Tseng Chih- Hung Lin Yng-Ruey Yuann F. Peter Tsai Lang-Chen Wang Show-Chyuan Chiang
Institute of Nuclear Energy Research, ROC No. 1000, Wenhua Rd., Jiaan Village, Longtan Township,Taoy Cool-Tec Co., USA TAIWAN POWER COMPANY
国际会议
上海
英文
482-494
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）