Abstract： In order to test heat shock resistance and operation stability of residual heat removal pump, thermal shock loop was designed based on energy conservation law and different working conditions of both coldstate and hotstate loops. The equipment types were determined by heat balance calculation. The thermal shock loop designed included both coldstate and hotstate loops, and intime switching experiment from coldstate to hotstate was carried out with a three way valve to simulate actual working conditions of residual heat removal pump. The experimental results show that the thermal shock loop system designed can really simulate practical working conditions of nuclear power plant. The equipment types are determined by heat balance calculation, and the heat shock resistance of pump parts is validated by means of convenient switching mode.
孔繁余， 王 婷， 黄道见， 王文廷. 核电站余热排出泵热冲击回路设计[J]. 排灌机械工程学报, 2010, 28(4): 291-294.
Kong Fanyu， Wang Ting， Huang Daojian， Wang Wenting. Design for thermal shock loop of residual heat removal pump in nuclear power plant . Journal of Drainage and Irrigation Machinery Engin, 2010, 28(4): 291-294.
[1]蔡龙,张丽平.浅谈压水堆核电站主泵[J].水泵技术,2007(4):1-5.Cai Long,Zhang Liping.Discussion about main pump used in pressurized water reactor nuclear power plant[J].Pump Technology,2007(4):1-5.(in Chinese)[2]朱荣生,管荣国,付强,等.核电站冷却水循环泵模型试验[J].排灌机械,2008,26(2):49-52.Zhu Rongsheng,Guan Rongguo,Fu Qiang,et al.Model experiment of circulating cooling water pump in nuclear power plant[J].Drainage and Irrigation Machinery,2008,26(2):49-52.(in Chinese)[3]彭德迟,余良旺.提高泵站供电系统可靠性的技术措施[J].排灌机械,2006,24(3):42-44.Peng Dechi,Yu Liangwang.Technical measures to improve reliability for pumping station power supply system[J].Drainage and Irrigation Machinery,2006,24(3):42-44.(in Chinese)[4]Tong L L,Lu F,Cao X W,et al.Thermal hydraulic behaviors during loss of RHR system at mid-loop operation of Chinese 300 MWe PWR NPP[J].Nuclear Enginee-ring and Design,2009,239(12):3027-3033.[5]Birchley J,Haste T J,Richner M.Accident management following loss of residual heat removal during mid-loop operation in a Westinghouse two-loop PWR[J].Nuclear Engineering and Design,2008,238(9):2173-2181.[6]国家医药管理局上海医药设计院.化工工艺设计手册[M].2版.北京:化学工业出版社,1996.[7]谭天恩,窦梅,周明华,等.化工原理[M].3版.北京:化学工业出版社,2006.[8]李世玉,桑如苞.压力容器工程师设计指南[M].北京:化学工业出版社,1994.
