溶液堆过量放射性释放风险的PSA事件树研究  

Research on PSA Event Tree of Excessive Radioactive Release Risk for Aqueous Homogeneous Reactor

作　　者：邹志强[1] 张丹[1] 刘余[1] 王宁宁 孙洪平 王喆 杨未东 都昱 Zou Zhiqiang;Zhang Dan;Liu Yu;Wang Ningning;Sun Hongping;Wang Zhe;Yang Weidong;Du Yu(State Key Laboratory of Advanced Nuclear Energy Technology,Nuclear Power Institute of China,Chengdu,610213,China;Nuclear and Radiation Safety Center,Ministry of Ecological Environment,Beijing,100082,China)

机构地区：[1]中国核动力研究设计院先进核能技术全国重点实验室,成都610213 [2]生态环境部核与辐射安全中心,北京100082

出　　处：《核动力工程》2024年第5期177-183,共7页Nuclear Power Engineering

摘　　要：溶液型医用同位素试验堆(简称溶液堆)的设计特点和安全特性与传统固体燃料压水堆存在显著差异,概率安全分析(PSA)的目的和范围也不相同,尤其是事件树分析。本文以溶液堆为研究对象,分析了其燃料形态、安全屏障及缓解系统等与传统压水堆的差异,确定了以过量放射性释放为分析目的的内部事件PSA需要考虑的放射性释放途径、包容边界以及主要的事故类型,建立了典型事故类的过量放射性释放通用事件树,可为该类型反应堆放射性释放风险PSA的开展和进一步的风险定量化提供指导。The design characteristics and safety features of aqueous homogeneous prototype medical isotope research reactor(AHR)are significantly different from those of traditional solid fuel pressurized water reactor,thus the purpose and range of probabilistic safety analysis(PSA)of these two kind of reactors,especially the event tree analysis are also different.Taking the AHR as the research object,the differences between its fuel form,safety barrier and mitigation system and that of the traditional PWR are analyzed.The radioactive release path,containment boundary and the main accident types that should be considered in the internal event PSA for the purpose of analysis of excessive radioactive release are determined,and the universal excessive radioactive release event trees of typical accident categories are constructed.The study can provide guidance for the PSA and further risk quantification of radioactive release risk of this type of reactor.

关 键 词：溶液型医用同位素试验堆(简称溶液堆) 概率安全分析(PSA) 内部事件PSA 事件树 过量放射性释放 

分 类 号：TL333[核科学技术—核技术及应用]