基于MAAP4的百万千瓦级核电站大破口事故分析  

Analysis of Large Breaks Accidents in 1000MW NPP Based on MAAP4

作　　者：袁显宝 林钦[1,2] 张彬航 刘芙蓉 俞玲 黄家胜[1,2] 夏寅泳 无 YUAN Xianbao;LIN Qin;ZHANG Binhang;LIU Furong;YU Ling;HUANG Jiasheng;XIA Yinyong;无(Mechanical and Power Engineering Subject of Three Gorges University,Ychong of Jiangsu Prov.443002,china;Hubei Key Laboratory of Hydroelectric Machinery Design & Maintenance,Three Gorges University,Yichang of Hubei Prov.443002 china;Wuhan Electric Power Vocational and Technical College,Wuhan of Hubei Prov.430079 china)

机构地区：[1]三峡大学机械与动力学院,江苏宜昌443002 [2]三峡大学湖北省水电机械设备设计与维护重点实验室,江苏宜昌443002 [3]武汉电力职业技术学院,湖北武汉430079

出　　处：《核科学与工程》2019年第5期789-795,共7页Nuclear Science and Engineering

基　　金：RHIC和LHC能区核核碰撞中奇异粒子产生特性的研究，11247021;湖北省水电机械设备设计与维护重点实验室开放基金（2016KJX15）;基于广义微扰理论的蒙特卡罗输运—燃耗耦合计算方法研究，1180511

摘　　要：本文采用严重事故一体化分析软件MAAP4(Modular Accident Analysis Program)对百万千瓦级压水堆进行分析,选取一回路大破口严重事故进行仿真,获得了该事故工况下核电厂关键参数的瞬态特性,与RELAP5计算结果进行了对比验证。在分析MAAP4模型的基础之上,进一步仿真该电站大破口事故后期进程,截取压力边界内外参数进行评估。分析结果表明:MAAP4在仿真安全壳和氢气分布上,预测事故结果置信度高,其中模拟的安全防护设计能够有效缓解事故进程,满足一般核电厂的安全评估要求,对概率安全评价(PSA)具有一定的参考意义。We use the severe accident analysis software MAAP4(Modular Accident Analysis Program)to analyze the 1000MW reactors.The large-breaks accident is selected for simulation,and the key parameters of nuclear power plant under the accident are obtained.The data are compared with the RELAP5 results.Based on the analysis of the MAAP4,the later process of the large breaks accident is further simulated,and the whole parameters of pressure boundary are intercepted for evaluation.The analysis results show that MAAP4 predicts the accident results with high confidence in the simulation of containment and hydrogen distribution.The simulated safety protection design can effectively alleviate the accident process and meet the safety assessment requirements of general nuclear power plants.Probabilistic safety assessment(PSA)has a certain reference significance.

关 键 词：严重事故 仿真分析 大破口 非能动安全 

分 类 号：TM623.8[电气工程—电力系统及自动化]