本文選題：主蒸汽隔離閥 + 振動疲勞��； 參考：《哈爾濱工程大學》2014年碩士論文

【摘要】：主蒸汽隔離閥是壓水堆核電站二回路關鍵設備之一,其主要功能是在主蒸汽管線發(fā)生破裂事故時進行主蒸汽隔離,防止事故進一步惡化。國內(nèi)某核電廠主蒸汽隔離閥在正常運行中出現(xiàn)噪聲和振動偏大的現(xiàn)象,而且在之后的大修期間,通過設備解體發(fā)現(xiàn)隔離閥閘板和安全閥閥內(nèi)構件出現(xiàn)不同程度的損傷。主蒸汽隔離閥造成的振動和噪聲偏大直接影響到主蒸汽管道、主蒸汽隔離閥以及主蒸汽安全閥的安全使用。因此,對主蒸汽隔離閥疲勞分析及壽命監(jiān)測系統(tǒng)研究對保證核電廠安全具有十分重要的意義。本文基于ASME核電廠運行與維修規(guī)范(ASME OM-S/G 2000 PART3),提出了改進型的振動應力以及振動疲勞壽命評估方法,并對主蒸汽隔離閥管系進行振動應力評估以及振動疲勞壽命評估。分析結(jié)果表明,管系結(jié)構頻率響應分析計算得到的振動交變應力大于規(guī)范中的允許值,進一步用頻域法對振動疲勞壽命評估結(jié)果表明,管系振動疲勞壽命高于設計壽命,有一定的安全裕量。另一方面,本文利用有限元接觸法對閘板和導向條進行非線性接觸分析,計算得到閘板和導向條的接觸壓力和滑移量以及危險截面的應力以及應變值。本文提出采用臨界面SWT法計算微動裂紋擴展方向以及預測微動疲勞壽命,計算及分析結(jié)果表明,微動疲勞裂紋萌生位置為閘板與導向條接觸邊緣位置。微動疲勞壽命預測結(jié)果表明在最大載荷下,對主蒸汽隔離閥運行留有較大安全裕量�；贚abVIEW虛擬儀器軟件設計了主蒸汽隔離閥疲勞壽命監(jiān)測系統(tǒng),仿真分析表明該系統(tǒng)能夠?qū)χ髡羝綦x閥疲勞壽命進行實時和離線監(jiān)測,并具有采樣誤差小、信噪比高的特點,可實現(xiàn)為運行人員提供直觀準確的壽命狀態(tài)顯示和狀態(tài)分析功能。本文的工作完善了核電廠主蒸汽隔離閥管系振動評估方法,對閥門閘板微動疲勞壽命預測提供了有效的方法。壽命監(jiān)測系統(tǒng)能為設備提供更加準確的壽命數(shù)據(jù),為核電廠設備的老化管理和延壽提供了數(shù)據(jù)支撐。
[Abstract]:The main steam isolating valve is one of the key equipments in the secondary circuit of PWR nuclear power station. Its main function is to isolate the main steam when the main steam pipeline ruptures to prevent the accident from getting worse. During the normal operation of the main steam isolating valve in a nuclear power plant in China, the phenomenon of noise and vibration is on the high side, and during the later overhaul, it is found that the isolating valve gate and the internal components of the safety valve are damaged to varying degrees through the disassembly of the equipment. The vibration and noise caused by the main steam isolation valve directly affect the safe use of the main steam pipe, the main steam isolation valve and the main steam safety valve. Therefore, it is very important to study the fatigue analysis and life monitoring system of the main steam isolating valve to ensure the safety of nuclear power plant. Based on the ASME OM-S / G 2000 PART3 code for the operation and maintenance of ASME nuclear power plant, this paper presents an improved method for evaluating vibration stress and vibration fatigue life, and evaluates the vibration stress and vibration fatigue life of the main steam isolation valve system. The analysis results show that the vibration alternating stress obtained by frequency response analysis of pipe system is greater than the allowable value in the code. Further, the frequency domain method is used to evaluate the vibration fatigue life. The results show that the vibration fatigue life of pipe system is higher than the design life. There is a certain safety margin. On the other hand, the finite element contact method is used to analyze the nonlinear contact between the sluice plate and the guide bar, and the contact pressure and slip of the gate and guide bar as well as the stress and strain values of the dangerous section are calculated. In this paper, the critical interface SWT method is used to calculate the direction of fretting crack propagation and to predict fretting fatigue life. The results of calculation and analysis show that the position of fretting fatigue crack initiation is the contact edge position between the gate and the guide strip. The prediction results of fretting fatigue life show that under the maximum load, a large safety margin is left for the operation of the main steam isolation valve. Based on LabVIEW virtual instrument software, the fatigue life monitoring system of main steam isolation valve is designed. The simulation results show that the system can monitor the fatigue life of main steam isolation valve in real time and offline, and has the characteristics of small sampling error and high signal-to-noise ratio. It can provide intuitive and accurate life state display and state analysis for operators. In this paper, the method of vibration evaluation of main steam isolating valve system in nuclear power plant is improved, which provides an effective method for predicting the fretting fatigue life of valve gate. Life monitoring system can provide more accurate life data for the equipment and provide data support for the aging management and life extension of nuclear power plant equipment.
【學位授予單位】：哈爾濱工程大學
【學位級別】：碩士
【學位授予年份】：2014
【分類號】：TM623.4

【參考文獻】

相關期刊論文 前9條

1 呂陽;夏虹;;基于振動信號的堆內(nèi)構件故障診斷研究[J];應用科技;2013年04期

2 杜永英;馬業(yè)鵬;鄢利群;;基于LabVIEW的旋轉(zhuǎn)機械振動狀態(tài)監(jiān)測及故障診斷系統(tǒng)設計[J];中國儀器儀表;2010年12期

3 姚起杭;姚軍;;工程結(jié)構的振動疲勞問題[J];應用力學學報;2006年01期

4 王建新,楊世鳳,史永江,童官軍;遠程監(jiān)控技術的發(fā)展現(xiàn)狀和趨勢[J];國外電子測量技術;2005年04期

5 鐘世梁,黃榮國,許冰;600MW機組高壓旁路減溫減壓閥熱應力計算及壽命估算[J];動力工程;2005年02期

6 羅桂娥,楊欣榮,陳明義,曾明;虛擬儀器技術在教學上的應用[J];電氣電子教學學報;2002年06期

7 林家浩,易平;線性隨機結(jié)構的平穩(wěn)隨機響應[J];計算力學學報;2001年04期

8 安剛,龔鑫茂;隨機振動環(huán)境下結(jié)構的疲勞失效分析[J];機械科學與技術;2000年S1期

9 鐘萬勰;一個高效結(jié)構隨機響應算法系列——虛擬激勵法[J];自然科學進展;1996年04期

相關碩士學位論文 前3條

1 李忷璐;基于LabVIEW的風力發(fā)電監(jiān)控系統(tǒng)的研究與應用[D];華北電力大學（北京）;2010年

2 韓福強;基于LabVIEW的泵站遠程監(jiān)控系統(tǒng)的研究[D];哈爾濱理工大學;2009年

3 王之華;基于LabVIEW的大型風力發(fā)電機組旋轉(zhuǎn)機械的狀態(tài)監(jiān)測系統(tǒng)設計[D];上海交通大學;2009年

，

本文編號：2045257