Study on Heat Removal Capability of Steam Generators During Loss of Residual Heat Removal System at Mid-loop Operation
(0) In the Pressurized Water Reactor (PWR) nuclear power plants, the risk of loss of residual heat removal system at mid-loop operation is very significant. Reflux-condensation is one of effective condensation mechanism during loss of residual heat removal system at mid-loop operation. By using SCDAP/RELAP5 code, thermal-hydraulic behaviors during loss of residual heat removal system at mid-loop operation when steam generator (SG) secondary side is under wet lay-up is analyzed for 300MW PWR nuclear power plant, to research the influence and heat removal capability of reflux-condensation in the SG U-tube. In this paper, three cases are considered to find the effect of reflux-condensation: a. both of steam generators are under wet lay-up, and closed primary system; b. one steam generator is under wet lay-up, the other is full of air, and closed primary system; c. both of steam generators are full of air, and closed primary system. The reason of considering closed primary system case is that this case makes the phenomenon and effect of reflux-condensation more obvious. Considering different number of SGs which are under wet lay-up is to research cooling capability of steam generators. Compare these calculation results with the cases without wet lay-up of SG secondary side, which shows that reflux-condensation in steam generator U-tube can delay the time of core uncovering, and remove core decay heat effectively.
Mid-loop operation Refluz-condensation SCDAP/RELAP5 code
Lu Fang Tong Li-li Zhang Kun Cao Xue-wu
School of nuclear science and engineering, Shanghai Jiao Tong University, Shanghai 200240, China
国际会议
ISSNP2008、CSEPC、ISOFIC2008(第二届21世纪和谐核电系统国际会议、第四届电厂控制中认知系统工程方法国际会议暨第三届未来核电厂仪表与控制国际会议)
哈尔滨
英文
208-212
2008-09-08（万方平台首次上网日期，不代表论文的发表时间）