摘要
为了避免类似福岛核泄漏事故的再次发生,各国在第三代核电机组的设计中,考虑采用非能动安全技术。非能动安全壳热量导出系统是我国“华龙一号”最重要的非能动安全系统之一,是实现最高核电建设标准的重要保障。本文主要从系统方案设计、内部换热器热工水力特性分析、系统综合性能实验和安全壳热工水力耦合特性实验等方面对非能动安全壳热量导出系统研究工作进行了总结,介绍了所开展研究的主要内容、所建实验装置的概况和得出的主要结论。上述理论分析和实验验证表明:所开发的非能动安全壳热量导出系统的排热能力远大于设计要求。
Passive safety technologies have been considered in the design of third-generation nuclear power units to avoid the recurrence of nuclear leakage accidents,such as the Fukushima incident.A passive containment heat removal system(PCS),in addition to being one of the most important passive safety systems of HPR1000,also serves as an important guarantee to achieve the highest nuclear power construction standards.This paper summarizes PCS research from the aspects of system scheme design,thermal hydraulic characteristic analysis of internal heat exchanger system,comprehensive performance experiment,and containment of thermal hydraulic coupling characteristic experiments.The important research content,experimental devices,and main conclusions are also presented.The above theoretical analysis and experimental verification indicate that the heat removal capacity of the developed PCS is substantially larger than the design requirements.
作者
邢继
孙中宁
于勇
丁铭
XING Ji;SUN Zhongning;YU Yong;DING Ming(China Nuclear Power Engineering Co.,Ltd.,Beijing 100840,China;College of Nuclear Science and Technology,Harbin Engineering University,Harbin 150001,China)
出处
《哈尔滨工程大学学报》
EI
CAS
CSCD
北大核心
2023年第7期1089-1095,共7页
Journal of Harbin Engineering University
基金
国家能源局
科学技术部
国家自然科学基金委
中国核工业集团有限公司给予的资金支持
中国核电工程有限公司
哈尔滨工程大学
关键词
“华龙一号”
非能动安全壳热量导出系统
开式自然循环
闭式自然循环
系统方案设计
内部换热器
综合性能实验
热工水力耦合特性
HPR1000
passive containment heat removal system
open natural circulation system
closed natural circulation system
system scheme design
internal heat exchanger
comprehensive performance experiment
thermal hydraulic coupling characteristics
