铅铋堆全厂断电事故下二次侧非能动余热排出系统特性研究  

Research on Characteristics of Secondary Side Passive Residual Heat Removal System of Lead-bismuth Reactor under SBO

作　　者：钱雅兰 林千[1] 杨子江 陈康 詹文辉[1] 汤春桃[1] 杨波[1] Qian Yalan;Lin Qian;Yang Zijiang;Chen Kang;Zhan Wenhui;Tang Chuntao;Yang Bo(Shanghai Nuclear Engineering Research&Design Institute Co.,Ltd.,Shanghai,200233,China)

机构地区：[1]上海核工程研究设计院股份有限公司,上海200233

出　　处：《核动力工程》2024年第4期32-37,共6页Nuclear Power Engineering

摘　　要：以俄罗斯SVBR-100铅铋堆二次侧非能动余热排出系统(PRHRS)为研究对象,采用RELAP5/MOD4.0程序建模开展全厂断电(SBO)事故下PRHRS的余热排出能力评价和参数敏感性分析。研究结果表明,在整个SBO事故中,关键参数燃料包壳峰值温度最高为816.35K,未超过安全限值,PRHRS能够及时导出堆芯余热;通过增大PRHRS水箱内置冷凝换热器换热面积可以增强PRHRS的余热排出能力。本研究建立的铅铋堆二次侧PRHRS安全分析模型和评价方法,可为我国铅铋堆PRHRS的设计和应用提供技术参考。The secondary side passive residual heat removal(PRHRS)of Russian SVBR-100 lead-bismuth reactor was chosen as the research object,and the RELAP5/MOD4.0 code was used to model and evaluate the heat removal capacity and parameter sensitivity of PRHRS under station blackout(SBO)accident.The results show that the key parameter of the peak cladding temperature is 816.35 K during the whole SBO accident,which is within the safety limit.PRHRS can timely remove the residual heat.By increasing the heat exchange area of the built-in condensing heat exchanger in PRHRS water tank,the residual heat removal capacity of PRHRS can be enhanced.The safety analysis model and evaluation method for secondary side PRHRS established in this study can provide technical reference for the design and application of PRHRS of lead-cooled reactor in China.

关 键 词：铅铋堆 非能动余热排出系统(PRHRS) 全厂断电(SBO)事故 RELAP5/MOD4.0 

分 类 号：TL333[核科学技术—核技术及应用]