小破口失水事故非能动系统瞬态特性研究  

Study on Coupling Characteristics of Small Break LOCA in Advanced PWR

作　　者：金远[1] 蒋孝蔚 邓坚[1] 刘余[1] 毕树茂[1] 朱大欢[1] 杨帆[1] Jin Yuan;Jiang Xiaowei;Deng Jian;Liu Yu;Bi Shumao;Zhu Dahuan;Yang Fan(Science and Technology on Reactor System Design Technology,Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213

出　　处：《核动力工程》2020年第2期189-192,共4页Nuclear Power Engineering

摘　　要：为了解先进压水堆小破口失水事故下非能动安全壳冷却系统、非能动堆芯冷却系统、非能动余热排出系统的瞬态响应特性,需开展小破口失水事故下反应堆冷却剂系统和安全壳的耦合响应特性研究。分析结果表明,小破口失水事故下,耦合分析中非能动余热排出系统、非能动堆芯冷却系统、自动卸压系统和非能动安全壳冷却系统的特性与独立计算有较大差异,小破口失水事故下耦合分析得到的安全壳压力峰值小于独立计算。In order to understand the transient response characteristics of the passive containment cooling system,the passive core cooling system and the passive residual heat removal system after the small break LOCA in an advanced pressurized water reactor,the coupling response characteristics of the reactor coolant system and the containment in SBLOCA are studied.The analysis results show that in the SBLOCA,the characteristics of the passive residual heat removal system,the passive core cooling system and the passive containment cooling system in the coupling analysis are quite different from the independent calculations.The containment peak pressure obtained by the coupling analysis in the SBLOCA is less than that by the independent calculation.

关 键 词：先进压水堆 耦合 小破口失水事故 

分 类 号：TL375[核科学技术—核技术及应用]