摘要
对于船用压水堆核动力装置,在保持一回路冷却剂平均温度恒定的基础上,使蒸汽发生器一次侧冷却剂流量随传热负荷变化,有可能实现蒸汽发生器运行压力恒定.本文探讨了冷却剂流量变化对蒸汽发生器传热特性的影响,讨论了实现双恒定运行方式所存在的几个问题.
For marine PWR nuclear power plant(NPP),it is probable to maintain the primary loop coolant average temperature and secondary loop steam pressure by controlling the coolant flow through the steam generator and varying directly as reactor power.In this paper,the relation of steam generator heat transfer coefficient to coolant flow is analyzed,and some questions around the steady state programming are discussed.
出处
《哈尔滨工程大学学报》
EI
CAS
CSCD
1998年第5期23-28,共6页
Journal of Harbin Engineering University