核電汽輪機側齒汽封流動特性的數(shù)值研究
發(fā)布時間:2018-12-15 01:52
【摘要】:核電站汽輪機汽封系統(tǒng)的蒸汽泄漏量對電廠經(jīng)濟性有重要影響,采用數(shù)值求解方法,用有限體積法對控制方程進行離散,并求解湍流模型的封閉方程組,分析了核電廠汽輪機上不同形式側齒汽封的流動特性和泄漏情況。結果表明:在不同的進口壓力下,單低齒側齒汽封的泄漏量低于雙低齒側齒汽封的泄漏量,有底齒的雙低齒側齒汽封和單低齒側齒汽封的泄漏量都略高于沒有底齒的。為優(yōu)化核電廠二回路汽封系統(tǒng)提供了理論參考。
[Abstract]:The steam leakage of steam seal system of nuclear power plant steam turbine has an important influence on the economy of power plant. The control equations are discretized by numerical method and finite volume method, and the closed equations of turbulent model are solved. The flow characteristics and leakage of different side teeth seal on nuclear power plant steam turbine are analyzed. The results show that under different inlet pressures, the leakage rate of single low tooth side tooth seal is lower than that of double low tooth side tooth seal, and the leakage rate of double low tooth side seal and single low tooth side tooth seal with bottom tooth is slightly higher than that of single low tooth side tooth seal. It provides a theoretical reference for optimizing the secondary loop steam seal system of nuclear power plant.
【作者單位】: 華北電力大學核科學與工程學院;華北電力大學核熱工安全與標準化研究所;非能動核能安全技術北京市重點實驗室;沈陽工程學院;
【基金】:中央高;究蒲袠I(yè)務專項資金項目(項目編號:2014BJ0086) 國家重點實驗室開發(fā)課題(項目編號:2014BJ0041)
【分類號】:TM623
,
本文編號:2379732
[Abstract]:The steam leakage of steam seal system of nuclear power plant steam turbine has an important influence on the economy of power plant. The control equations are discretized by numerical method and finite volume method, and the closed equations of turbulent model are solved. The flow characteristics and leakage of different side teeth seal on nuclear power plant steam turbine are analyzed. The results show that under different inlet pressures, the leakage rate of single low tooth side tooth seal is lower than that of double low tooth side tooth seal, and the leakage rate of double low tooth side seal and single low tooth side tooth seal with bottom tooth is slightly higher than that of single low tooth side tooth seal. It provides a theoretical reference for optimizing the secondary loop steam seal system of nuclear power plant.
【作者單位】: 華北電力大學核科學與工程學院;華北電力大學核熱工安全與標準化研究所;非能動核能安全技術北京市重點實驗室;沈陽工程學院;
【基金】:中央高;究蒲袠I(yè)務專項資金項目(項目編號:2014BJ0086) 國家重點實驗室開發(fā)課題(項目編號:2014BJ0041)
【分類號】:TM623
,
本文編號:2379732
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