Influence of steam generator outlet pipe parameters on inlet flow field of nuclear reactor coolant pump
LIU Cong1,WANG Yuehui1,MA Tengyue1,WANG Pengfei2,XU Zhongbin1*,RUAN Xiaodong3
1. Institute of Process Equipment, Zhejiang University, Hangzhou, Zhejiang 310027, China; 2. School of Engineering, Zhejiang University City College, Hangzhou, Zhejiang 310015, China; 3. State Key Laboratory of Fluid Power Transmission and Control, Zhejiang University, Hangzhou, Zhejiang 310027, China
Abstract：According to the scale model experiment, it is found that the outlet pipe of the steam gene-rator(SG)has an obvious non-uniform inflow. In order to study the influence of the SG outlet pipe parameters on the inlet flow field of nuclear reactor coolant pump(RCP), a unified model of the SG lo-wer head and the RCP was established, and the three-dimensional flow field was simulated by CFD method. The results show that the outlet pipe length of the SG has a great influence on the inlet flow field of the RCP, and the influence is particularly obvious when the inlet pipe is shorter. With the increase of the pipe length of the SG, the influence gradually decreases, and the inlet flow field of the RCP tends to be stable. The location of the outlet pipe of the SG has little influence on the flow field turbulence of the RCP inlet, and the development trend of the flow field in the different positions of the tube is similar, but it will have a great impact on the position of the high-speed and the low-speed regions of the flow field. The flow field in the outlet pipe of the SG is extremely disordered, and there is a large recirculation zone at the beginning. With the development of the flow field, the reflux phenomenon disappears around 350 mm from the SG outlet, and then the flow field becomes stable gradually, but the eccentricity of the flow field will not disappear.
[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 on the main pump of PWR nuclear power plant [J]. Pump technology, 2007(4): 1-5.(in Chinese)[2]张明乾, 刘昱, 李承亮. 浅谈压水堆核电站 AP1000 屏蔽式电动主泵[J]. 水泵技术, 2008(4): 1-5. ZHANG Mingqian, LIU Yu, LI Chengliang. Discussion on AP1000 shielded electric main pump for PWR nuclear power station [J]. Pump Technology, 2008(4): 1-5.(in Chinese)[3]侯向陶, 王鹏飞, 许忠斌, 等. 蒸汽发生器下封头对核主泵入口流场影响[J]. 排灌机械工程学报, 2016, 34(4): 277-282. HOU Xiangtao, WANG Pengfei, XU Zhongbin, et al. Influence of steam generator channel head on reactor coolant pump inflow field[J].Journal of drainage and irrigation machinery engineering, 2016, 34(4): 277-282.(in Chinese)[4]施卫东, 张光建, 张德胜, 等. 入口非均匀流对轴流泵性能和压力脉动的影响[J]. 排灌机械工程学报, 2014, 32(4): 277-282. SHI Weidong, ZHANG Guangjian, ZHANG Desheng, et al. Effects of non-uniform suction flow on performance and pressure fluctuation in axial-flow pumps [J].Journal of drainage and irrigation machinery enginee-ring, 2014, 32(4): 277-282.(in Chinese)[5]VAN ESCH B P M. Performance and radial loading of a mixed-flow pump under non-uniform suction flow[J]. Journal of fluids engineering, 2009, 131(5): 051101.[6]DUAN X, MAO G, YAN J, et al. Study on the characteristic of self-excited cavitation oscillation in pump-ping system [J]. Advanced materials research, 2011, 268:148-153.[7]CHENG H, LI H, YIN J, et al. Investigation ofthe distortion suction flow on the performance of the canned nuclear coolant pump[C]//Procedings of ISFMFE—international Symposium on Fluid Machinery & Fluid Engineering. IET, 2014.[8]LONG Y, WANG D, YIN J, et al. Experimental investigation on the unsteadypressure pulsation of reactor coolant pumps with non-uniform inflow[J]. Annals of nuclear energy, 2017, 110: 501-510.[9]LONG Y, WANG D, YIN J, et al. Numerical investigation on the unsteady characteristics of reactor coolant pumps with non-uniform inflow[J]. Nuclear engineering and design, 2017, 320: 65-76.[10]夏栓, 冯斌, 张海军. AP1000核岛主泵流场数值模拟[J]. 核技术, 2013, 36(4): 101-107. XIA Shuan, FENG Bin, ZHANG Haijun. Simulation of AP1000 reactor coolant pump flow field CFD [J]. Nuclear techniques, 2013, 36(4): 101-107.(in Chinese)[11]WANG Y, WANG P, TAN X, et al. Research on the non-uniform inflow characteristics of the canned nuclear coolant pump[J]. Annals of nuclear energy, 2018, 115:423-429.[12]王少明, 郝建立, 章德,等. 蒸汽发生器U型管单相流动不稳定性分析[J]. 原子能科学技术, 2016, 50(5): 819-822. WANG Shaoming, HAO Jianli, ZHANG De,et al. Single phase flow instability analysis in steam generator U-tube[J]. Atomic energy science and technology, 2016, 50(5): 819-822.(in Chinese)[13]孟剑, 徐金康. AP1000 反应堆蒸汽发生器的设计特点[J]. 发电设备, 2015, 29(1): 35-39. MENG Jian, XU Jinkang. Design features of the AP1000 PWR steam generator[J]. Power equipment, 2015, 29(1): 35-39.(in Chinese)[14]侯向陶. 蒸汽发生器下封头对核主泵性能影响研究[D]. 杭州:浙江大学, 2016.[15]姜茂华. 核主泵水力部件优化设计及缩尺模型水力试验[D]. 杭州:浙江大学,2014.[16]马腾跃. 核主泵与蒸汽发生器流场耦合特性研究[D].杭州:浙江大学,2018.[17]GONZÁLEZ J, SANTOLARIA C. Unsteady flow stru-cture and global variables in a centrifugal pump[J]. Journal of fluids engineering, 2006, 128(5):937-946.
