基于双向流固耦合的核主泵叶轮力学特性  

Mechanical properties of nuclear reactor coolant pump impeller based on bidirectional fluid structure interaction

作　　者：钟伟源 朱荣生[1] 王秀礼[1] 卢永刚[1] 刘永[1] 康俊鋆 ZHONG Weiyuan;ZHU Rongsheng;WANG Xiuli;LU Yonggang;LIU Yong;KANG Junjun(National Research Center of Pumps, Jiangsu University, Zhenjiang, Jiangsu 212013, China)

机构地区：[1]江苏大学国家水泵及系统工程研究中心,江苏镇江212013

出　　处：《排灌机械工程学报》2018年第6期479-487,共9页Journal of Drainage and Irrigation Machinery Engineering

基　　金：国家自然科学基金资助项目(51379091;51509112);江苏省重点研发计划项目(BE2016160);江苏省产学研前瞻性联合研究项目(BY2016072-02);江苏省自然科学基金项目(BK20130516);江苏省普通高校研究生科研创新计划项目(KYLX16_0894)

摘　　要：基于双向流固耦合方法对核主泵内流场和结构场进行联合求解,研究流固耦合作用下核主泵叶轮的力学特性,分析经流固耦合作用后叶轮总体、叶片进出口边及叶根在各流量下的应力及变形分布.研究结果表明流固耦合作用对核主泵外特性有一定影响且耦合后结果更接近试验值;随着流量的增加,叶轮前盖板处应力分布均匀性有所降低,而叶轮的最大等效应力均发生在叶轮叶片出口边与叶轮前盖板交界处,在交变载荷的作用下容易产生疲劳破坏.叶轮的最大的变形发生在叶轮叶片出水边的中部,叶轮的最大变形量随着流量的增加而增大.叶根的进出口边处易出现应力集中现象,说明叶片进出口边对液流的压力载荷及动静干涉作用极为敏感,在叶轮水力及结构设计时应予以足够重视.研究结果为核主泵以后的性能分析、叶轮的结构设计、维护和检修提供了有益参考.Based on the bidirectional fluid structure interaction method,the flow field and the structural response of the impeller were solved. The mechanical properties of the impeller of the nuclear reactor coolant pump were studied. The stress and deformation distributions of the impeller,the leading and trailing of the blade,and the root of the blade under different flows were analyzed. The results show that the fluid structure interaction effect has some influence on the characteristics of the nuclear reactor coolant pump and the result is closer to the test value after coupling. With the increase of flow rate,the stress distribution uniformity of the front shroud decreases,and the maximum equivalent stress occurs at the trailing edge of impeller blade and the frond shroud at the junction,where the fatigue load is liable to occur under the alternating load. The maximum deformation of the impeller occurs at the middle of the exit edge of the blade,which increases with flow rate. The stress concentration phenome-non appears easily at the leading and trailing of the blade root,which shows that the inlet and outlet of the blade are very sensitive to the pressure,load,static and dynamic interference of the fluid flow.Therefore,enough attention should be paid to these areas in impeller＇s hydraulic and structural design.The results provide a useful reference for the performance analysis of the nuclear reactor coolant pump as well as the structural design,maintenance and overhaul of the impeller.

关 键 词：核主泵 双向流固耦合 动应力 变形 数值模拟 

分 类 号：TH313[机械工程—机械制造及自动化]