大型压水堆核电厂事故暂态运行特性研究  

Study on Large Scale Pressurized Water Reactor Nuclear Power Plant Accident Transient Operating Characteristics

作　　者：欧阳利平[1] 刘涤尘[1] 赵洁[1] 云雷[1] 董超[1] 

机构地区：[1]武汉大学电气工程学院,湖北武汉430072

出　　处：《陕西电力》2012年第4期53-57,共5页Shanxi Electric Power

基　　金：国家自然科学基金项目(51077103)

摘　　要：核电是1种新能源,核电厂的安全稳定运行受到社会的广泛关注。文中利用PCTRAN软件仿真分析了WWER1000核电厂-回路失水、蒸汽管道破裂及蒸汽发生器传热管断裂事故,研究了核电厂的事故过程及暂态运行特性,比较分析了不同破口的失水事故、蒸汽管道破裂事故以及单根和多根蒸汽发生器传热管断裂事故时核电厂暂态运行特性。结果表明:核电厂发生大破口失水事故、蒸汽管道大破裂事故及多根U型传热管完全断裂事故可能会对核电厂安全产生较严重影响,同时,核电厂内部发生严重事故导致核电厂紧急停堆、停机,对电网会造成影响。Nuclear power is a new energy,the safe and stable operation of the nuclear power plant （NPP） have raised an extensive attention around the world. Based on PCTRAN, this paper studies the second-generation nuclear power reactor type WWERI000 aecidents transient operation eharacteristic, the loss of coolant aceident, the steam pipe rupture accident and the steam generatnr tube rupture accident of WWER1000 reactor type primary eoolant cireuit are analyzed, different size of loss of coolant accident ,different size of steam pipe rupture accident and single and muhi-rnot steam generator lube rupture accident of nuclear accidents transient operation characteristic are compared and analyzed. The results show that large size break of loss of coolant accident, large break of steam pipe rupture accident and multi-root steam generator tube rupture accident have an great impact on NPP safety, at the same time, a serious accident happen inside the NPP may lead to emergency shutdown, and would affect the power grid.

关 键 词：压水堆核电机组 异常事故 仿真计算 暂态特性 

分 类 号：TM613[电气工程—电力系统及自动化]