压水堆核电站二回路蒸汽循环及其改进  

The Steam Cycle of PWR Secondary System and Its Improvement

作　　者：吴存真[1] 肖杰[1] 屠传经 

机构地区：[1]浙江大学能源系

出　　处：《核动力工程》1994年第5期454-459,共6页Nuclear Power Engineering

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。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.

关 键 词：核电站 二回路 蒸汽循环 压水型堆 

分 类 号：TL353[核科学技术—核技术及应用]