压水堆核电AP1000二回路系统与1000MW超超临界机组热力系统的比较  

Contrast of Secondary Circuit System of PWR Nuclear Power AP1000 and Thermal Power System of 1 000 MW Ultra Supercritical Unit

作　　者：叶成 张震 李云胜 李献斌 

机构地区：[1]中国电能成套设备有限公司,北京市100011 [2]山东核电有限公司,山东省海阳市264000

出　　处：《电力设备》2008年第4期25-28,共4页Electrical Equipment

摘　　要：文章介绍了压水堆核电AP1000与1000MW超超临界机组热力系统及主要参数,并从郞肯循环、末级叶片、旁路系统、效率与流量方面进行了比较。AP1000二回路蒸汽参数比超超临界机组蒸汽参数低,其汽轮机旁路系统功能多、容量大,AP1000系统的热效率为36·6%,而1000MW超超临界火电机组电厂热效率可达45%以上。The article briefs the thermal power systems and main parameters of PWR nuclear power plant AP1000 and 1 000 MW ultra supercritical unit and conduct the contrast in terms of Rankine cycle,last stage blade,bypass system,efficiency and flow rate.The steam parameters of AP1000 secondary circuit are lower than those of ultra supereritical unit,and the bypass system of its steam turbine has many functions and large capacity;the thermal efficiency of AP1000 system is 36.6%,while the thermal efficiency of 1 000 MW ultra supercrifical fossil-fired unit may reach more than 45%.

关 键 词：核电 超超临界 热力系统 旁路系统 

分 类 号：TK212[动力工程及工程热物理—动力机械及工程]