“华龙一号”设计基准事故辐照鉴定剂量研究  

Study on Design Basis Accident Irradiation Dose Assessment for HPR1000

作　　者：唐辉 金鑫 秦戈 徐教珅 韩继伟 TANG Hui;JIN Xin;QIN Ge;XU Jiaoshen;HAN Jiwei(China Nuclear Power Design Co.,Ltd.(Shenzhen),Shenzhen of Guangdong Prov.518026,China)

机构地区：[1]深圳中广核工程设计有限公司,广东深圳518000

出　　处：《核科学与工程》2024年第4期738-743,共6页Nuclear Science and Engineering

摘　　要：为了确定“华龙一号”设备辐照鉴定的技术要求,需要对“华龙一号”设计基准事故下安全壳内的辐照源项和剂量进行评估。本文对事故后辐照源项的释放和迁移机理进行了研究,提出了安全壳内设计基准事故源项和剂量评估的总体方法步骤,同时对计算中的关键现象和计算假设进行了研究和确定。通过本研究,制定了一套评估“华龙一号”安全壳内设计基准事故源项和剂量的方法和假设,并对“华龙一号”设备鉴定的剂量要求进行了确定。In order to determine the technical requirements for irradiation qualification of HPR1000,it is necessary to evaluate the source term and dose inside the containment under the design basis accident of HPR1000.This paper studies the release and migration mechanisms of the accidental source term and proposes a general methodology for evaluating the design basis accident source term and dose inside the containment.The key phenomena and assumptions in the calculations are also studied and determined.Through this study,a set of methodologies and assumptions for evaluating the design basis accident source term and dose inside the HPR1000 containment are established,and dose requirements for the equipment qualification of HPR1000 are formulated.

关 键 词：设计基准事故 设备鉴定 辐照源项 剂量 

分 类 号：TL48[核科学技术—核技术及应用]