【摘要】：核主泵是核電站反應(yīng)堆中關(guān)鍵部件之一,其作用是驅(qū)動(dòng)反應(yīng)堆冷卻劑在一回路中流動(dòng),帶走堆芯中因核反應(yīng)釋放的熱量。AP1000核主泵是應(yīng)用于第三代先進(jìn)核電技術(shù)即非能動(dòng)型壓水堆核電技術(shù)的主泵。大流量、高可靠性和低維護(hù)率是核主泵永遠(yuǎn)追求的目標(biāo)。本論文圍繞大流量下高效水力模型開展研究。 本文的設(shè)計(jì)方法是速度系數(shù)法,比較國(guó)外AP1000核主泵設(shè)計(jì)的速度系數(shù)與國(guó)內(nèi)已有設(shè)計(jì)案例選擇的速度系數(shù),尋找國(guó)內(nèi)現(xiàn)階段應(yīng)用速度系數(shù)法進(jìn)行核主泵葉輪設(shè)計(jì)的不足之處,從而對(duì)現(xiàn)階段速度系數(shù)表進(jìn)行改進(jìn)使之更加符合實(shí)際情況與設(shè)計(jì)需要。初步設(shè)計(jì)的葉輪經(jīng)數(shù)值計(jì)算效率為89.51%,效率偏低,需要對(duì)其改型設(shè)計(jì)。利用BVF方法對(duì)初步設(shè)計(jì)的葉片進(jìn)行診斷分析,在不改變軸面尺寸下,通過改進(jìn)葉片進(jìn)出口邊形狀和葉片背弧型線,效率大幅提高為94.34%。對(duì)改進(jìn)的葉輪模型進(jìn)行了網(wǎng)格無關(guān)性的驗(yàn)證,和不同湍流模式預(yù)測(cè)精度的對(duì)比。 國(guó)外AP1000葉輪的進(jìn)出口角度未知,為了找到最佳的進(jìn)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?nèi)~片進(jìn)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(chǔ)上,對(duì)導(dǎo)葉和蝸殼進(jìn)行設(shè)計(jì)研究。本文通過改變導(dǎo)葉數(shù)和導(dǎo)葉進(jìn)口角度,以及導(dǎo)葉進(jìn)口邊相對(duì)位置,發(fā)現(xiàn)導(dǎo)葉數(shù)目和導(dǎo)葉進(jìn)口角度的變化對(duì)泵水力性能影響較小,導(dǎo)葉進(jìn)口邊與軸線平行時(shí)的水力性能要好于導(dǎo)葉進(jìn)口邊與葉輪出口邊平行情況。并對(duì)蝸殼出口位置進(jìn)行研究,發(fā)現(xiàn)側(cè)向出口蝸殼性能要好于中心出口。在此基礎(chǔ)上對(duì)泵整體變工況性能分析,最大效率點(diǎn)在設(shè)計(jì)流量下,揚(yáng)程隨流量單調(diào)下降未出現(xiàn)駝峰。在此基礎(chǔ)上,考慮了葉頂泄漏對(duì)核主泵的影響。 為了核主泵的安全穩(wěn)定運(yùn)行,需要對(duì)泵內(nèi)動(dòng)靜之間產(chǎn)生的壓力脈動(dòng)和徑向力進(jìn)行分析,發(fā)現(xiàn)x和y方向的徑向力合力只與工作轉(zhuǎn)頻有關(guān),和葉片與導(dǎo)葉個(gè)數(shù)關(guān)系不大。葉片和導(dǎo)葉之間相互影響,在葉片中出現(xiàn)了由導(dǎo)葉個(gè)數(shù)引起的脈動(dòng)頻率,導(dǎo)葉中也出現(xiàn)由葉片個(gè)數(shù)引起的脈動(dòng)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(shè)計(jì)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(shè)計(jì)及優(yōu)化提供了建設(shè)性的意見,為核主泵的后續(xù)研究奠定基礎(chǔ)。
[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(xué)位授予單位】：大連理工大學(xué)
【學(xué)位級(jí)別】：碩士
【學(xué)位授予年份】：2012
【分類號(hào)】：TH311

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相關(guān)期刊論文 前6條

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本文編號(hào)：2284817