摘要
非能动安全壳热量导出系统(PCS)是华龙一号(HPR1000)设计用来应对超设计基准事故工况的安全系统。本文描述了该系统总体配置方案的形成过程,分析了系统在缓解超设计基准事故工况及严重事故工况时的有效性,并从概率安全分析指引的角度,分析了系统对核电厂堆芯损坏频率和放射性物质大量释放频率的影响作用。结果表明:PCS对于提升HPR1000的严重事故预防和缓解能力具有明显的效果,可有效提升HPR1000的安全性。
Passive containment heat removal system（PCS）is used to deal with the beyond design basic accidents of HPR1000.The general configuration of the system was described,and then the effectiveness of this system to deal with beyond design basic accident and severe accident was analyzed.Based on probabilistic safety analysis,the impact of PCS on core damage frequency and large radioactive release frequency was analyzed.The results show that PCS has a significant effect on enhancing the prevention and mitigation of severe accidents of HPR1000 and can effectively enhance the safety of HPR1000.
作者
李军
李晓明
喻新利
刘长亮
LI Jun1,2,LI Xiaoming3,YU Xinli4,LIU Changliang4(1. Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin 150001, China , 2. Hualong Pressurized Water Reactor Technology Corporation, Ltd., Beijing 100087, China , 3. China National Nuclear Corporation, Beijing 100822, China , 4. China Nuclear Power Engineering Co., Ltd., Beijing 100840, Chin)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2018年第6期1021-1027,共7页
Atomic Energy Science and Technology
关键词
非能动安全壳热量导出系统
可靠性
概率安全分析
passive containment heat removal system
reliability
probabilistic safetyanalysis
