会议专题

CFD Simulation of the Thermal-Hydraulic Characteristics within Spent Fuel Storage Pool

The spent fuel rods unloaded from reactor core have massive decay heat and are temporarily stored in the spent fuel pool. It is important for the safety operation of nuclear power plant to determine whether it has proper capability to remove the decay heat. The objective of the present study is to research the residual heat removal ability of spent fuel pool under various unloaded scenarios and influences of various arrangements of inlet pipe. CFD methodology was applied to develop a tool for spent fuel pool thermal hydraulic analysis. The heat transfer at the interface air/ liquid was modeled by using effective heat transfer coefficient, which was attained by considering the heat transfer including the natural convection of the air and the vapor of hot water. Results show that the arrangement of the inlet pipe located at the bottom of the spent fuel storage pool, considering the capacity of removing decay heat, is superior to all other arrangements. Both under normal conditions and even more severe scenarios, cooling system can remove the remaining residual heat and the peak temperature locates at the top region of spent fuel storage rack. There exit strong natural circulation, which enhances the flow and heat transfer process in the storage pool. The present studies are of great significance and can provide valuable references for the design and optimization of spent fuel storage pool.

Fluent Spent fuel storage pool Natural convection CFD Effective heat transfer coefficient

YE Shui-xiang ZENG He-yi GUO Yun Gong Cheng

College of Nuclear Science and Technology, Harbin Engineering University, P.R. China, 150001

国际会议

2011 China Located International Conference on Information Systems for Crisis Response and Management(第五届危机响应与管理信息系统中国区国际大会 ISCRAM-China 2011)

哈尔滨

英文

582-592

2011-11-24(万方平台首次上网日期,不代表论文的发表时间)