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压水堆核电站二回路蒸汽循环及其改进
引用本文:吴存真,肖杰.压水堆核电站二回路蒸汽循环及其改进[J].核动力工程,1994,15(5):454-459.
作者姓名:吴存真  肖杰
作者单位:浙江大学能源系
摘    要:本文分析了压水堆核电站二回路饱和蒸汽循环的系统热效率及汽轮机高、低压缸排汽湿度与新蒸汽初参数、汽轮机分缸压力比之间的关系.在与他和蒸汽循环比较的基础上,分析了微过热蒸汽循环的系统热效率和高、低压缸排汽湿度受新蒸汽初压、初温及汽轮机分缸压力比的影响。在此基础上,给出了两种循环的比较结果及循环的最佳运行参数范围。

关 键 词:核电站  二回路  蒸汽循环  压水型堆

The Steam Cycle of PWR Secondary System and Its Improvement
Wu Cunzhen, Xiao Jie, Tu Chuanjing.The Steam Cycle of PWR Secondary System and Its Improvement[J].Nuclear Power Engineering,1994,15(5):454-459.
Authors:Wu Cunzhen  Xiao Jie  Tu Chuanjing
Abstract:The relation between the thermodynamic effeciency of saturated steam cycle in PWR secondary system and the steam humidity at the exit of high pressure turbine (HPT) and lowpressure turbine (LPT) and live steam parameters of the cycle pressure ratio of HPT and LPTinlet are analysed. The influence of live steam parameters and pressure ratio of HPT to LPTinlet on the thermodynamic effeciency of superheat steam cycle in the PWR secondary systemand the steam humidity at IIPT and LPT exit are investigated. The optimum operating parameters region and conclusions of comparing superheat steam cycle with saturated steam cycle arepresented.
Keywords:Nuclear power station Pressure Water reactor Secondary system Steam cycle Saturated steam Superheated steam  
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