原子能科学技术2018，Vol.52Issue(6)：1021-1027,7.DOI:10.7538/yzk.2017.youxian.0609
非能动安全壳热量导出系统设计方案及评价
Design and Evaluation of Passive Containment Heat Removal System
李军 1李晓明 2喻新利 3刘长亮4
作者信息
- 1. 哈尔滨工程大学 核安全与仿真技术国防重点学科实验室,黑龙江 哈尔滨 150001
- 2. 华龙国际核电技术有限公司,北京 100037
- 3. 中国核工业集团公司,北京 100822
- 4. 中国核电工程有限公司,北京 100840
- 折叠
摘要
Abstract
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 ana-lyzed.T he 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 H PR1000.关键词
非能动安全壳热量导出系统/可靠性/概率安全分析Key words
passive containment heat removal system/reliability/probabilistic safety analysis分类
能源科技引用本文复制引用
李军,李晓明,喻新利,刘长亮..非能动安全壳热量导出系统设计方案及评价[J].原子能科学技术,2018,52(6):1021-1027,7.
