AP1000与EPR机组在役检查的差异性比较与分析  

Analysis and Comparison about In-service Inspection Difference between AP1000 and EPR

作　　者：王臣[1] 孙海涛[1] 盛朝阳[1] 高晨[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082

出　　处：《核安全》2015年第1期38-44,共7页Nuclear Safety

基　　金：大型先进压水堆科技重大专项之内陆厂址环境评价关键技术研究;课题编号2009ZX06004-022

摘　　要：定期对核电厂实施在役检查是保障核电厂安全运行的重要手段之一。本文通过对国内第三代核电机组适用的在役检查相关法规标准的解读,结合AP1000机组与EPR机组的机械设备核心设备的各自设计特点,分析比较两者包括检查项目、在役检查周期和验收标准等在役检查活动的差异性,并对两者的在役检查活动提出改进建议。In-service inspection is one of important methods to guarantee the safety of nuclear power plants. With the study of the codes and standards for the in-service inspection（ISI）of the domestic third generation nuclear power units and combining the design characteristic of AP1000 and EPR,the differences of ISI activities between AP1000 and EPR such as inspection items,inspection interval and acceptance criteria were analyzed and compared. Some suggestions were provided.

关 键 词：AP1000 EPR 在役检查 差异性 

分 类 号：TL386[核科学技术—核技术及应用]