AP1000核主泵的优化设计及试验研究  

Optimization Design and Test Research of AP1000 Nuclear Reactor Coolant Pump

作　　者：付强[1] 习毅[1] 朱荣生[1] 王秀礼[1] 

机构地区：[1]江苏大学流体机械工程技术研究中心,江苏镇江212013

出　　处：《原子能科学技术》2015年第9期1648-1654,共7页Atomic Energy Science and Technology

基　　金：国家自然科学基金资助项目(51379091);江苏省自然科学基金资助项目(BK2013516);江苏高校优势学科建设工程资助项目(PAPD);国家博士后基金资助项目(2014M551551)

摘　　要：根据核主泵的设计参数,采用正交试验对核主泵的主要参数进行了初步正交优化设计。根据正交优化结果,得到了1组最佳几何参数组合及各主要参数对核主泵性能影响的主次顺序,根据主次影响顺序对主要影响因素进行了进一步的多方案优化设计,进而得到能使核主泵具有更好性能的叶轮几何设计参数组合。根据最终的叶轮几何设计参数,建立了三维模型及对其内部流场进行了数值模拟计算,并用相似换算法,设计制造出对应的模型泵进行试验研究。结果显示:试验结果和模拟结果基本吻合,由此可证明叶轮优化设计的正确性。According to the design parameters of nuclear reactor coolant pump ,the pre‐liminary orthogonal optimization design for main parameters which had influence on the performance of nuclear reactor coolant pump were made by using orthogonal test . According to the results of orthogonal optimization design ,a set of the best combination of geometrical parameters and the primary and secondary influence order of the main parameters for the nuclear reactor coolant pump were got .According to the order ,the further optimization design of several main parameters was made ,and the combination of geometry design parameter for impeller was lastly achieved . The three‐dimensional model was established , the inner flow field was simulated , the model pump was designed and manufactured by using similar conversion method and the test research in normal temperature and pressure was done .The results show that the simulation results＆nbsp;are similar to the test results ,so it shows that the orthogonal optimization design is right .

关 键 词：核主泵 正交试验 优化设计 

分 类 号：TH313[机械工程—机械制造及自动化]