秦山核电二期工程失水事故分析  

Analysis of Loss of Coolant Accident for Qinshan Phase II NPP Project

作　　者：王荣忠[1] 王勇[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2003年第z1期51-55,共5页Nuclear Power Engineering

摘　　要：失水事故是核电站设计的基准事故之一,是压水堆事故分析关注的重点。本文概括介绍了秦山核电二期工程的失水事故分析及分析计算所使用的计算程序;简要地描述了MEFRA-1等计算程序的特点。重点介绍了大破口失水事故分析,给出了分析计算的主要假设条件和分析计算结果。分析计算表明,大破口失水事故工况下,燃料元件最大峰值包壳表面温度为1092.56℃,秦山核电二期工程的安全注射系统能保证该核电站在发生失水事故时的安全。Loss of coolant accident is considered as design basis accident in the design of nuclear power plant. It is the key point of accident analysis for pressurized water reactor plant. This paper generally describes the contents of LOCA analysis for Qinshan Phase II NPP Project and characteristic of MEFRA-1 computer code. Large break LOCA is specially introduced in this paper. Main assumptions and calculation results are provided in detail. Maximum fuel cladding temperature is about 1092.56℃.The safety injection system of Qinshan Phase II NPP Project can ensure the plant safety in the loss of coolant accident.

关 键 词：失水事故 分析 MEFRA-1程序 安全注射系统 堆芯再淹没 

分 类 号：TM623[电气工程—电力系统及自动化] TL364+.4[核科学技术—核技术及应用]