核电汽轮机侧齿汽封流动特性的数值研究
发布时间：2018-12-15 01:52
【摘要】：核电站汽轮机汽封系统的蒸汽泄漏量对电厂经济性有重要影响,采用数值求解方法,用有限体积法对控制方程进行离散,并求解湍流模型的封闭方程组,分析了核电厂汽轮机上不同形式侧齿汽封的流动特性和泄漏情况。结果表明:在不同的进口压力下,单低齿侧齿汽封的泄漏量低于双低齿侧齿汽封的泄漏量,有底齿的双低齿侧齿汽封和单低齿侧齿汽封的泄漏量都略高于没有底齿的。为优化核电厂二回路汽封系统提供了理论参考。
[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.
【作者单位】： 华北电力大学核科学与工程学院;华北电力大学核热工安全与标准化研究所;非能动核能安全技术北京市重点实验室;沈阳工程学院;
【基金】：中央高校基本科研业务专项资金项目(项目编号:2014BJ0086) 国家重点实验室开发课题(项目编号:2014BJ0041)
【分类号】：TM623
，
本文编号：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.
【作者单位】： 华北电力大学核科学与工程学院;华北电力大学核热工安全与标准化研究所;非能动核能安全技术北京市重点实验室;沈阳工程学院;
【基金】：中央高校基本科研业务专项资金项目(项目编号:2014BJ0086) 国家重点实验室开发课题(项目编号:2014BJ0041)
【分类号】：TM623
，
本文编号：2379732
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