CAP1000核电厂全功率范围SGTR事故研究  

Study of SGTR Accident in Wide Power Range for CAP1000

作　　者：柯晓[1,2] 

机构地区：[1]上海核工程研究设计院,上海200233 [2]上海交通大学机械与动力工程学院,上海200240

出　　处：《原子能科学技术》2014年第6期1031-1037,共7页Atomic Energy Science and Technology

摘　　要：对CAP1000非能动核电厂在部分功率、零功率和热备用条件下发生的蒸汽发生器传热管破裂(SGTR)事故进行蒸汽发生器满溢评价。对典型的部分功率、零功率和热备用运行条件下的SGTR事故分别进行横向敏感性分析,选取每个运行条件下的保守工况,结合满功率事故工况进行纵向功率谱对比,根据其瞬态特性,分析事故进程,评价极限运行工况和关键参数。结果表明:CAP1000核电厂在全功率范围内发生SGTR事故均不会导致蒸汽发生器满溢,且最严重的工况发生在满功率条件下。The steam generator overfilling of CAP1000 nuclear power plant in steam generator tube rupture （SGTR） accident was analyzed .The power range for this analy-sis included typical part-power ,zero power and hot standby .The sensitivity analyses were compared at each power level .And the conservative case at every power level was selected to contrast with the result of full power .Based on the transient characteristics , the accident processes were analyzed ,and then the limiting case and critical parameters were evaluated .It turns out that the steam generator of CAP1000 will not be overfilled in SGTR accident which is assumed to occur in entire power range ,and the most limit-ing case appears in full power condition .

关 键 词：蒸汽发生器传热管破裂 部分功率 零功率 热备用 满溢 

分 类 号：TL333[核科学技术—核技术及应用]