發(fā)布時間：2018-10-21 10:26

【摘要】：核主泵是核電站反應堆中關鍵部件之一,其作用是驅動反應堆冷卻劑在一回路中流動,帶走堆芯中因核反應釋放的熱量。AP1000核主泵是應用于第三代先進核電技術即非能動型壓水堆核電技術的主泵。大流量、高可靠性和低維護率是核主泵永遠追求的目標。本論文圍繞大流量下高效水力模型開展研究。 本文的設計方法是速度系數(shù)法,比較國外AP1000核主泵設計的速度系數(shù)與國內已有設計案例選擇的速度系數(shù),尋找國內現(xiàn)階段應用速度系數(shù)法進行核主泵葉輪設計的不足之處,從而對現(xiàn)階段速度系數(shù)表進行改進使之更加符合實際情況與設計需要。初步設計的葉輪經(jīng)數(shù)值計算效率為89.51%,效率偏低,需要對其改型設計。利用BVF方法對初步設計的葉片進行診斷分析,在不改變軸面尺寸下,通過改進葉片進出口邊形狀和葉片背弧型線,效率大幅提高為94.34%。對改進的葉輪模型進行了網(wǎng)格無關性的驗證,和不同湍流模式預測精度的對比。 國外AP1000葉輪的進出口角度未知,為了找到最佳的進出口匹配角,引入了Kriging優(yōu)化算法,在不改變軸向尺寸的條件下,通過不斷改變葉片進出口角度,得到了最優(yōu)的葉片匹配角,優(yōu)化后效率為95.56%,優(yōu)化效果明顯。 在此基礎上,對導葉和蝸殼進行設計研究。本文通過改變導葉數(shù)和導葉進口角度,以及導葉進口邊相對位置,發(fā)現(xiàn)導葉數(shù)目和導葉進口角度的變化對泵水力性能影響較小,導葉進口邊與軸線平行時的水力性能要好于導葉進口邊與葉輪出口邊平行情況。并對蝸殼出口位置進行研究,發(fā)現(xiàn)側向出口蝸殼性能要好于中心出口。在此基礎上對泵整體變工況性能分析,最大效率點在設計流量下,揚程隨流量單調下降未出現(xiàn)駝峰。在此基礎上,考慮了葉頂泄漏對核主泵的影響。 為了核主泵的安全穩(wěn)定運行,需要對泵內動靜之間產(chǎn)生的壓力脈動和徑向力進行分析,發(fā)現(xiàn)x和y方向的徑向力合力只與工作轉頻有關,和葉片與導葉個數(shù)關系不大。葉片和導葉之間相互影響,在葉片中出現(xiàn)了由導葉個數(shù)引起的脈動頻率,導葉中也出現(xiàn)由葉片個數(shù)引起的脈動頻率。變工況非定常與定常特性曲線在大流量下差距很大,小流量和設計流量差距不大。 本文的研究工作在一定程度上為核主泵的設計及優(yōu)化提供了建設性的意見,為核主泵的后續(xù)研究奠定基礎。
[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.
【學位授予單位】：大連理工大學
【學位級別】：碩士
【學位授予年份】：2012
【分類號】：TH311

【參考文獻】

相關期刊論文 前6條

1 韓永志;高行山;李立州;岳珠峰;;基于Kriging模型的渦輪葉片多學科設計優(yōu)化[J];航空動力學報;2007年07期

2 郭鵬程,羅興，

本文編號：2284817