基于速度系数法的AP1000核主泵水力部件设计与优化
发布时间：2018-10-21 10:26
【摘要】：核主泵是核电站反应堆中关键部件之一,其作用是驱动反应堆冷却剂在一回路中流动,带走堆芯中因核反应释放的热量。AP1000核主泵是应用于第三代先进核电技术即非能动型压水堆核电技术的主泵。大流量、高可靠性和低维护率是核主泵永远追求的目标。本论文围绕大流量下高效水力模型开展研究。 本文的设计方法是速度系数法,比较国外AP1000核主泵设计的速度系数与国内已有设计案例选择的速度系数,寻找国内现阶段应用速度系数法进行核主泵叶轮设计的不足之处,从而对现阶段速度系数表进行改进使之更加符合实际情况与设计需要。初步设计的叶轮经数值计算效率为89.51%,效率偏低,需要对其改型设计。利用BVF方法对初步设计的叶片进行诊断分析,在不改变轴面尺寸下,通过改进叶片进出口边形状和叶片背弧型线,效率大幅提高为94.34%。对改进的叶轮模型进行了网格无关性的验证,和不同湍流模式预测精度的对比。 国外AP1000叶轮的进出口角度未知,为了找到最佳的进出口匹配角,引入了Kriging优化算法,在不改变轴向尺寸的条件下,通过不断改变叶片进出口角度,得到了最优的叶片匹配角,优化后效率为95.56%,优化效果明显。 在此基础上,对导叶和蜗壳进行设计研究。本文通过改变导叶数和导叶进口角度,以及导叶进口边相对位置,发现导叶数目和导叶进口角度的变化对泵水力性能影响较小,导叶进口边与轴线平行时的水力性能要好于导叶进口边与叶轮出口边平行情况。并对蜗壳出口位置进行研究,发现侧向出口蜗壳性能要好于中心出口。在此基础上对泵整体变工况性能分析,最大效率点在设计流量下,扬程随流量单调下降未出现驼峰。在此基础上,考虑了叶顶泄漏对核主泵的影响。 为了核主泵的安全稳定运行,需要对泵内动静之间产生的压力脉动和径向力进行分析,发现x和y方向的径向力合力只与工作转频有关,和叶片与导叶个数关系不大。叶片和导叶之间相互影响,在叶片中出现了由导叶个数引起的脉动频率,导叶中也出现由叶片个数引起的脉动频率。变工况非定常与定常特性曲线在大流量下差距很大,小流量和设计流量差距不大。 本文的研究工作在一定程度上为核主泵的设计及优化提供了建设性的意见,为核主泵的后续研究奠定基础。
[Abstract]:The nuclear main pump is one of the key components in the nuclear power plant reactor. Its function is to drive the flow of reactor coolant in the primary circuit. AP1000 nuclear main pump is the main pump used in the third generation advanced nuclear power technology, I. e., inactive PWR nuclear power technology. High flow rate, high reliability and low maintenance rate are the goal of nuclear pump. This paper focuses on the research of high efficiency hydraulic model under large discharge. The design method of this paper is the velocity coefficient method, comparing the speed coefficient of the AP1000 main pump design abroad with the speed coefficient selected by the existing design cases in China, and looking for the deficiency of the impeller design of the nuclear main pump using the velocity coefficient method at the present stage in our country. Thus, the speed coefficient table is improved to meet the actual situation and design needs. The numerical calculation efficiency of the primary designed impeller is 89.51, and the efficiency is low, so it is necessary to modify the design of the impeller. The BVF method is used to diagnose and analyze the primary design blade. Without changing the axial dimension, the efficiency is improved to 94.34 by improving the shape of the inlet and outlet edge of the blade and the back arc line of the blade. The improved impeller model is verified by grid independence and compared with the prediction accuracy of different turbulence models. The inlet and outlet angle of AP1000 impeller is unknown. In order to find the best matching angle, the Kriging optimization algorithm is introduced. The optimal blade matching angle is obtained by constantly changing the blade inlet and outlet angle without changing the axial dimension. The optimized efficiency is 95.566.The effect of optimization is obvious. On this basis, the guide vane and volute are designed and studied. By changing the number of guide vane, the inlet angle of guide vane and the relative position of inlet edge of guide vane, it is found that the number of guide vane and the inlet angle of guide vane have little influence on the hydraulic performance of pump. When the inlet edge of the guide vane is parallel to the axis, the hydraulic performance is better than that of the inlet edge of the guide vane and the outlet edge of the impeller. It is found that the lateral outlet volute is better than the central outlet. On the basis of the analysis of the overall performance of the pump under variable working conditions, the maximum efficiency point is at the design flow rate, and the hump does not appear when the head monotonously decreases with the flow rate. On this basis, the effect of tip leakage on nuclear pump is considered. For the safe and stable operation of the nuclear main pump, the pressure pulsation and radial force produced between the static and static of the pump need to be analyzed. It is found that the resultant force of the radial force in the x and y directions is only related to the frequency conversion of the work, and the number of the vane and the guide vane is not related to the resultant force. The pulsation frequency caused by the number of the guide vane and the pulsation frequency caused by the number of the blades also appeared in the blade and the guide vane influenced by each other. The difference between the unsteady and steady characteristic curves of variable working conditions is very large under the large flow rate, but the gap between the small flow rate and the design flow rate is not large. The research work in this paper provides constructive suggestions for the design and optimization of nuclear main pump to a certain extent and lays a foundation for further study of nuclear main pump.
【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
[Abstract]:The nuclear main pump is one of the key components in the nuclear power plant reactor. Its function is to drive the flow of reactor coolant in the primary circuit. AP1000 nuclear main pump is the main pump used in the third generation advanced nuclear power technology, I. e., inactive PWR nuclear power technology. High flow rate, high reliability and low maintenance rate are the goal of nuclear pump. This paper focuses on the research of high efficiency hydraulic model under large discharge. The design method of this paper is the velocity coefficient method, comparing the speed coefficient of the AP1000 main pump design abroad with the speed coefficient selected by the existing design cases in China, and looking for the deficiency of the impeller design of the nuclear main pump using the velocity coefficient method at the present stage in our country. Thus, the speed coefficient table is improved to meet the actual situation and design needs. The numerical calculation efficiency of the primary designed impeller is 89.51, and the efficiency is low, so it is necessary to modify the design of the impeller. The BVF method is used to diagnose and analyze the primary design blade. Without changing the axial dimension, the efficiency is improved to 94.34 by improving the shape of the inlet and outlet edge of the blade and the back arc line of the blade. The improved impeller model is verified by grid independence and compared with the prediction accuracy of different turbulence models. The inlet and outlet angle of AP1000 impeller is unknown. In order to find the best matching angle, the Kriging optimization algorithm is introduced. The optimal blade matching angle is obtained by constantly changing the blade inlet and outlet angle without changing the axial dimension. The optimized efficiency is 95.566.The effect of optimization is obvious. On this basis, the guide vane and volute are designed and studied. By changing the number of guide vane, the inlet angle of guide vane and the relative position of inlet edge of guide vane, it is found that the number of guide vane and the inlet angle of guide vane have little influence on the hydraulic performance of pump. When the inlet edge of the guide vane is parallel to the axis, the hydraulic performance is better than that of the inlet edge of the guide vane and the outlet edge of the impeller. It is found that the lateral outlet volute is better than the central outlet. On the basis of the analysis of the overall performance of the pump under variable working conditions, the maximum efficiency point is at the design flow rate, and the hump does not appear when the head monotonously decreases with the flow rate. On this basis, the effect of tip leakage on nuclear pump is considered. For the safe and stable operation of the nuclear main pump, the pressure pulsation and radial force produced between the static and static of the pump need to be analyzed. It is found that the resultant force of the radial force in the x and y directions is only related to the frequency conversion of the work, and the number of the vane and the guide vane is not related to the resultant force. The pulsation frequency caused by the number of the guide vane and the pulsation frequency caused by the number of the blades also appeared in the blade and the guide vane influenced by each other. The difference between the unsteady and steady characteristic curves of variable working conditions is very large under the large flow rate, but the gap between the small flow rate and the design flow rate is not large. The research work in this paper provides constructive suggestions for the design and optimization of nuclear main pump to a certain extent and lays a foundation for further study of nuclear main pump.
【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
【参考文献】
相关期刊论文 前6条
1 韩永志;高行山;李立州;岳珠峰;;基于Kriging模型的涡轮叶片多学科设计优化[J];航空动力学报;2007年07期
2 郭鹏程,罗兴，
本文编号：2284817
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