天堂国产午夜亚洲专区-少妇人妻综合久久蜜臀-国产成人户外露出视频在线-国产91传媒一区二区三区

核主泵導葉壓水室結構對水力性能影響分析與研究

發(fā)布時間:2018-06-08 02:48

  本文選題:核主泵 + 壓力脈動 ; 參考:《大連理工大學》2014年碩士論文


【摘要】:核主泵作為核島一回路內(nèi)唯一轉動部件,擁有核島“心臟”之稱。由于國外的技術壟斷,并對我國實行技術封鎖,核主泵一直是我國核電技術自主化和設備國產(chǎn)化的發(fā)展瓶頸。因此,要實現(xiàn)自主創(chuàng)新,研發(fā)具有自主知識產(chǎn)權的安全、高效、長服役壽命的核主泵,就必須對核主泵流動特性及結構特性有明確的認識和深入研究。 本文采用CFD技術并結合水力性能試驗,圍繞著CAP1400核主泵模型泵內(nèi)部定常非定常流動展開,通過對其性能及流動規(guī)律的深入研究分析,著重探討了模型泵流動性能和對壓力脈動的改善,本文所得結論可為CAP1400核主泵進一步的設計及優(yōu)化提供理論與試驗支持。 首先,本文對CAP1400核主泵模型泵進行定常全工況數(shù)值模擬,對比試驗結果分析了模型泵整機全流量工況性能與流動規(guī)律,結果表明泵性能優(yōu)異,數(shù)值方法得當。在此基礎上,給出不同流量工況下模型泵內(nèi)部非定常壓力脈動時域頻域分布規(guī)律,為本文后續(xù)工作做準備。 其次,針對CAP1400模型泵流動情況不良區(qū)域,給出了導葉周向旋轉、切割及非均布柵距導葉等方案,采用數(shù)值模擬對比幾種方案的性能,并就非均布柵距導葉方案進行多工況非定常數(shù)值分析,給出了與原模型對比分析結果。結果表明導葉周向旋轉、截短導葉及導葉非均布都能在一定程度上改善泵壓水室出口附近流動,特別地,非均布導葉能改變由動靜干涉產(chǎn)生的脈動頻率分布,大幅削弱甚至消除導葉通頻、倍頻脈動幅值,有助于降低核主泵振動及噪聲,提高核主泵運行安全性。 最后,本文對壓水室出流管位置,壓水室進流位置及環(huán)形壓水室截面積對核主泵性能的影響展開數(shù)值研究。結果表明壓水室中心進流、側向出流擁有更好的流動性能,傳統(tǒng)速度系數(shù)法設計的壓水室容易使泵最優(yōu)點向小流量偏移。
[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.
【學位授予單位】:大連理工大學
【學位級別】:碩士
【學位授予年份】:2014
【分類號】:TL353.12

【參考文獻】

相關期刊論文 前10條

1 伍浩松;王海丹;郭志鋒;;世界核電現(xiàn)狀[J];國外核新聞;2013年06期

2 張野;王曉放;介紅恩;;壓水堆冷卻劑中硼酸濃度對核主泵性能影響研究[J];核動力工程;2011年04期

3 徐朝暉,吳玉林,陳乃祥,劉宇,張梁;高速泵內(nèi)三維非定常動靜干擾流動計算[J];機械工程學報;2004年03期

4 劉陽;袁壽其;袁建平;;離心泵的壓力脈動研究進展[J];流體機械;2008年09期

5 吳賢芳;劉厚林;談明高;崔建保;丁劍;;離心泵關死點內(nèi)部流動數(shù)值模擬[J];農(nóng)業(yè)機械學報;2013年11期

6 朱躍;尹俊連;張繼革;王德忠;程輝;;屏蔽式核主泵進出口壓力脈動特性[J];核技術;2013年11期

7 袁向陽;;CAP1400核電常規(guī)島主給水泵水力性能數(shù)值模擬與優(yōu)化[J];科學技術與工程;2014年01期

8 朱榮生;鄭寶義;李小龍;付強;;1000MW級核主泵內(nèi)部非定常流動特性[J];熱能動力工程;2012年03期

9 秦武;李志鵬;沈宗沼;靳衛(wèi)華;;核反應堆冷卻劑循環(huán)泵的現(xiàn)狀及發(fā)展[J];水泵技術;2007年03期

10 趙養(yǎng)正;劉前智;廖明夫;;非均勻柵距對壓氣機葉片非定常氣動力的影響[J];推進技術;2007年02期

,

本文編號:1994080

資料下載
論文發(fā)表

本文鏈接:http://sikaile.net/falvlunwen/zhishichanquanfa/1994080.html


Copyright(c)文論論文網(wǎng)All Rights Reserved | 網(wǎng)站地圖 |

版權申明:資料由用戶99dc4***提供,本站僅收錄摘要或目錄,作者需要刪除請E-mail郵箱bigeng88@qq.com