AP1000核主泵高效水力模型设计与性能研究

发布时间：2018-01-10 22:07

本文关键词：AP1000核主泵高效水力模型设计与性能研究　出处：《大连理工大学》2012年硕士论文　论文类型：学位论文

【摘要】：在压水堆核电站中,一回路循环的工质水与核反应堆直接接触,吸收和传递大量的热量,工质工作温度、压力变得很高,工作流量很大,还具有放射性,因此与之匹配的驱动冷却剂工质循环的核主泵具有高温高压大流量的特征。核主泵作为核岛内唯一高速运转的装备,无论是从安全性还是从性能上,对它的要求都比普通水泵高很多,其核心设计和制造技术目前被国外一些国家垄断,并严格保密,我国并未掌握,在这种背景下,如何突破国外的技术封锁,实现核主泵的国产化设计制造等问题就突现出来。本文探索了AP1000三代核主泵高效水力部件的设计方法,完善了之前研究提出的基于CFD的核主泵模化设计方法,对由7叶片叶轮、18叶片导叶以及中心出口蜗壳构成的核主泵整机进行了设计与分析,最终获得的核主泵水力模型具有最佳的动静叶片数匹配,较优良的水力特性和抗汽蚀特性,为三代核主泵的国产化设计做出了初步尝试。首先,本文利用之前研究提出的基于CFD的核主泵模化设计方法讨论了核主泵叶轮改变叶片数的模化设计问题,并因此扩展了该方法的应用范围,总结出改变叶轮叶片数后带来的设计问题。在这一部分,将之前研究设计得到的AP1000核主泵叶轮叶片数从5片改为7片,并利用三种湍流模型k-ε、SA、SST模型对核主泵内部流动进行三维数值模拟,同时分析其水力特性和空化特性,再根据内部流动分析寻找合适的优化策略,优化7叶片叶轮的叶片型线和进口角度。结果表明,策略得当,效果明显。然后,本文从动静叶片数匹配的角度完成了核主泵18叶片导叶的设计,从保证运行可靠性与安全性的角度完成了核主泵中心出口等截面蜗壳的设计。采用Harmonic非定常算法计算分析了核主泵叶轮与导叶之间的动静叶干涉效应,重点研究了叶轮与导叶径向间隙对泵性能的影响以及整机的全工况性能。文中兼顾泵的扬程与效率要求,认为间隙为15-17mm时核主泵性能最佳,这为以后的设计提供了有益参考。计算得到的整机全工况性能曲线趋势较好,水力效率达到86%,所设计的核主泵整机模型满足了核主泵苛刻的水动力强度、汽蚀、水力等要求。最后,本文对不同功率要求的核主泵整机设计进行了尝试,研究发现基于CFD的核主泵模化设计方法虽然是在叶轮设计过程中提出的,但是可以推广到整机设计。通过AP1200、AP1400核主泵的尝试设计,表明完善后的基于CFD的模化设计方法,其突出特点是能够方便地完成整机(包括叶轮、导叶、蜗壳)的设计,能遗传模型泵的优良性能,并简化设计过程,缩短设计周期。
[Abstract]:The nuclear main pump is the only high - speed running equipment in the nuclear island . The nuclear main pump is the only high - speed operating equipment in the nuclear island . In this paper , the design method of the high - efficiency hydraulic component of the AP1000 nuclear main pump is explored , and the design and analysis of the nuclear main pump based on CFD in the previous study are perfected . The main pump hydraulic model composed of 7 blade impeller , 18 blade guide vane and central outlet volute is designed and analyzed . The final nuclear main pump hydraulic model has the best dynamic and static blade number matching , excellent hydraulic characteristics and cavitation erosion characteristics , and makes a preliminary attempt for the localization design of the three - generation nuclear main pump . First , the modeling design of the impeller of the nuclear main pump is discussed in this paper , and the application range of the method is extended , and the design problems caused by changing the number of blades of the impeller are summarized . In this part , the three turbulence models k - 蔚 , SA and SST are used to simulate the internal flow of the nuclear main pump . The blade profile and the inlet angle of the 7 blade impeller are optimized according to the internal flow analysis . The results show that the strategy is good and the effect is obvious . In this paper , the design of the blade guide vane of the nuclear main pump is completed from the angle of the number matching of the dynamic and static blades . The effect of the radial clearance between the impeller and the guide vane of the nuclear main pump is calculated from the angle of ensuring the operation reliability and the safety . The effect of the radial clearance between the impeller and the guide vane on the performance of the pump and the full working condition of the whole machine are analyzed . Finally , the design of the nuclear main pump with different power requirements is attempted . It is found that the design method of the nuclear main pump based on CFD is proposed in the design of the impeller , but it can be extended to the design of the whole machine . Through the design of AP1200 and AP1400 nuclear main pump , it shows that the improved CFD - based modeling design method can easily complete the design of the whole machine ( including the impeller , guide vane and volute ) , and can simplify the design process and shorten the design cycle .

【学位授予单位】：大连理工大学
【学位级别】：硕士
【学位授予年份】：2012
【分类号】：TH311

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