Abstract:To study the influence of different positions of guide vane trailing edge on the pressure fluctuation and gas fraction fluctuation in volute wall of nuclear reactor coolant pump under gasliquid phase condition, and find a best position of guide vane trailing edge, the threedimensional numerical software CFX was used to simulate the internal transient flow field of pump, with monitoring points set in different positions, in the hope of learning pressures and gas fraction distributions at different times and different positions within each model pump. By comparing pressure fluctuations, frequency domains and time domains at the same position of each model, it was found that the pressure is lower and steadier when the guide vane trailing edge is in the center plane of volute. In another word, the vibration and noise caused by pressure fluctuation were lower; it is the best position for safety. At the same time, it was also found that the fluctuation frequency of volute wall was influenced by impeller rotation frequency. Except similar tongue, impeller rotation almost has little effect on gas fraction distribution of volute wall and outlet.
[1]秦武,李志鹏,沈宗沼,等.核反应堆冷却剂循环泵的现状及发展[J].水泵技术,2007(3):1-6.Qin Wu,Li Zhipeng,Shen Zongzhao,et al.Actuality and development of the nuclear reactor coolant pump[J].Pump Technology,2007(3):1-6. (in Chinese)[2]Poullikkas A.Two phase flow performance of nuclear reaction coolant pumps[J]. Progress in Nuclear Energy, 2000,36(2): 123-130.[3]Poullikkas. Effects of twophase liquidgas flow on the performance of nuclear reactor cooling pumps[J]. Nuclear Energy, 2003,42(1):3-10.[4]Rahim F C, Mohammad Rahgoshay, Seyed Khalil Mousavian. A study of large break LOCA in the AP1000 reactor containment[J]. Progress in Nuclear Energy,2012, 54(1):132-137.[5]王春林,彭娜,赵佰通,等. 核主泵模型泵导叶进口边相对位置对泵性能的影响[J]. 排灌机械, 2008, 26(5):38-41.Wang Chunlin, Peng Na, Zhao Baitong, et al. Influence of relative position of diffuser inlet edge on performance of nuclear model pump[J]. Drainage and Irrigation Machinery, 2008, 26(5):38-41.(in Chinese)[6]Rzentkowski G, Zbroja S. Acoustic characterization of a CANDU primary heat transport pump at the bladepassing frequency[J]. Nuclear Engineering and Design, 2000, 196(1): 63-68.[7]朱荣生, 郑宝义, 李小龙,等. 1 000 MW 级核主泵内部非定常流动特性[J]. 热能动力工程,2012, 27 (3):377-382.Zhu Rongsheng, Zheng Baoyi, Li Xiaolong, et al. Study on unsteady flow characteristics of 1 000 MW nuclear reactor coolant pump[J].Journal of Engineering for Thermal Energy and Power, 2012, 27 (3):377-382.(in Chinese)[8]丛国辉,王福军. 双吸离心泵隔舌区压力脉动特性分析[J]. 农业机械学报, 2008, 39 (6):60-63.Cong Guohui, Wang Fujun. Numerical investigation of unsteady pressure fluctuations near volute tongue in a double suction centrifugal pump[J].Transactions of Chinese Society for Agricultural Machinery,2008, 39 (6):60-63.(in Chinese)[9]黄思,吴玉林. 离心泵全三维流场的大涡数值模拟[J]. 华南理工大学学报:自然科学版,2006,34 (4):111-114.Huang Si, Wu Yulin. Largeeddy numerical simulation of threedimension flow in centrifugal pump[J].Journal of South China University of Technology:Natural Science Edition,2006,34 (4):111-114.(in Chinese)