CPR1000与AP1000安全系统的差异性比较和分析  

Comparison and Analysis of Differences between CPR1000 and AP1000 Safety Systems

作　　者：苏晋 SU Jin(Nuclear Nuclear Power Operations Management Co., Ltd., Jiaxing, Zhejiang 314300, China)

机构地区：[1]中核核电运行管理有限公司,浙江嘉兴314300

出　　处：《科技视界》2018年第3期126-128,共3页Science & Technology Vision

摘　　要：作为非能动设计的代表堆型——AP1000,其安全系统设计理念与传统核电站存在着很大的区别。本文从CPR1000堆型的安全注入系统以及AP1000的非能动堆芯冷却系统的系统组成、系统功能和系统运行几个方面着手,进行一个简要的介绍,在介绍的同时对比二者之间存在的差异,并对相应的差异进行比较分析,供核电专业技术人员参考。As the representative reactor design of APAM,the design concept of safety system is quite different from the traditional nuclear power plant.In this paper,a brief introduction is given from the aspects of system configuration,system function and system operation of the CPR1000reactor safety injection system and AP1000passive core cooling system.The differences between the two are introduced,And comparative analysis of the corresponding differences for nuclear power professional and technical personnel for reference.

关 键 词：CPR1000 AP1000 非能动堆芯冷却系统 安全注入系统 差异 

分 类 号：TG316[金属学及工艺—金属压力加工]