核主泵导叶压水室结构对水力性能影响分析与研究

发布时间：2018-06-08 02:48

本文选题：核主泵 + 压力脉动　；参考：《大连理工大学》2014年硕士论文

【摘要】：核主泵作为核岛一回路内唯一转动部件,拥有核岛“心脏”之称。由于国外的技术垄断,并对我国实行技术封锁,核主泵一直是我国核电技术自主化和设备国产化的发展瓶颈。因此,要实现自主创新,研发具有自主知识产权的安全、高效、长服役寿命的核主泵,就必须对核主泵流动特性及结构特性有明确的认识和深入研究。本文采用CFD技术并结合水力性能试验,围绕着CAP1400核主泵模型泵内部定常非定常流动展开,通过对其性能及流动规律的深入研究分析,着重探讨了模型泵流动性能和对压力脉动的改善,本文所得结论可为CAP1400核主泵进一步的设计及优化提供理论与试验支持。首先,本文对CAP1400核主泵模型泵进行定常全工况数值模拟,对比试验结果分析了模型泵整机全流量工况性能与流动规律,结果表明泵性能优异,数值方法得当。在此基础上,给出不同流量工况下模型泵内部非定常压力脉动时域频域分布规律,为本文后续工作做准备。其次,针对CAP1400模型泵流动情况不良区域,给出了导叶周向旋转、切割及非均布栅距导叶等方案,采用数值模拟对比几种方案的性能,并就非均布栅距导叶方案进行多工况非定常数值分析,给出了与原模型对比分析结果。结果表明导叶周向旋转、截短导叶及导叶非均布都能在一定程度上改善泵压水室出口附近流动,特别地,非均布导叶能改变由动静干涉产生的脉动频率分布,大幅削弱甚至消除导叶通频、倍频脉动幅值,有助于降低核主泵振动及噪声,提高核主泵运行安全性。最后,本文对压水室出流管位置,压水室进流位置及环形压水室截面积对核主泵性能的影响展开数值研究。结果表明压水室中心进流、侧向出流拥有更好的流动性能,传统速度系数法设计的压水室容易使泵最优点向小流量偏移。
[Abstract]:The nuclear main pump, as the only rotating part in the nuclear island's primary circuit, is known as the "heart" of the island. Because of the foreign technology monopoly and the technology blockade on our country, the nuclear main pump has always been the bottleneck of the development of nuclear power technology autonomy and equipment localization in our country. Therefore, in order to achieve independent innovation and develop a nuclear master pump with independent intellectual property rights that is safe, efficient and has a long service life, It is necessary to have a clear understanding and in-depth study on the flow characteristics and structural characteristics of the nuclear main pump. In this paper, CFD technique and hydraulic performance test are used to carry out the steady unsteady flow in the model pump of CAP1400 nuclear main pump. Through the in-depth study and analysis of its performance and flow law, the flow performance of the model pump and the improvement of the pressure pulsation are emphatically discussed. The conclusions obtained in this paper can provide theoretical and experimental support for the further design and optimization of the CAP1400 nuclear main pump. In this paper, the model pump of CAP1400 core pump is numerically simulated under steady operating conditions. The performance and flow law of the model pump are analyzed by comparing the experimental results. The results show that the pump has excellent performance and proper numerical method. On this basis, the time-domain frequency domain distribution of unsteady pressure pulsation in the model pump under different flow conditions is given, which will prepare for the subsequent work in this paper. Secondly, the circumferential rotation of the guide vane is given in view of the bad flow area of CAP1400 model pump. Numerical simulation is used to compare the performance of several schemes for cutting and non-uniform grid distance guide vane, and the unsteady numerical analysis of non-uniform grid distance guide vane scheme is carried out under various working conditions, and the results are compared with the original model. The results show that the circumferential rotation of guide vane, truncated guide vane and non-uniform distribution of guide vane can improve the flow near the outlet of pump pressure water chamber to some extent. In particular, the non-uniform guide vane can change the pulsating frequency distribution caused by static and dynamic interference. It is helpful to reduce the vibration and noise of the nuclear main pump and improve the safety of the nuclear main pump. Finally, the location of the outlet tube of the pressurized water chamber is discussed. The influence of inlet position of pressurized water chamber and cross section area of annular water chamber on the performance of nuclear main pump was studied numerically. The results show that the flow in the center of the pressurized water chamber and the lateral outlet flow have better fluidity, and the water pressure chamber designed by the traditional velocity coefficient method is easy to make the pump's best point deviate to the small flow rate.
【学位授予单位】：大连理工大学
【学位级别】：硕士
【学位授予年份】：2014
【分类号】：TL353.12

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