三代压水堆核电站核岛主设备安全特征分析  

Safety Feature Analysis of Primary Components in Third Generation Pressurized Water Reactor Nuclear Power Plant

作　　者：孙海涛[1] 李海龙[1] 盛朝阳[1] 高晨[1] 王臣[1] 凌礼恭[1] 贾盼盼[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082

出　　处：《核科学与工程》2015年第3期493-497,共5页Nuclear Science and Engineering

摘　　要：为了满足"三代"核电技术要求,三代压水堆核电站核岛主设备在容量、设计寿命和安全裕量等方面均进行了优化设计。本文对AP1000和EPR等机型核岛主设备的技术特征、改进目标和改进方法等进行了分析,为核电厂的设备运行和改造、新电厂的设计提供参考。The designs such as capacity, design life and safety margin of primary components have been optimized in the third generation pressurized water reactor nuclear power plant, in order to meet the requirements of ＂Third Generation＂ nuclear power technology. Technical features, improvement objectives and improvement methods of primary components for AP1000 and EPR are analyzed to provide reference for equipment operation, reformation and design of new nuclear power plant.

关 键 词：三代压水堆 先进轻水堆用户要求文件 AP1000 EPR 

分 类 号：TL353[核科学技术—核技术及应用]