CFETR氦冷包层放射性废物包装容器的屏蔽设计  

Shielding design of container for radioactive waste of CFETR helium cooling blanket

作　　者：赵自强 栗再新[1] 曹启祥[1] ZHAO Zi-qiang;LI Zai-xin;CAO Qi-xiang(Southwestern Institute of Physics,Chengdu 610041)

机构地区：[1]核工业西南物理研究院,成都610041

出　　处：《核聚变与等离子体物理》2022年第2期175-181,共7页Nuclear Fusion and Plasma Physics

基　　金：国家重点研发计划(2017YFE0300502)。

摘　　要：对中国聚变工程实验堆(CFETR)氦冷陶瓷产氚包层放射性废物包装容器进行了屏蔽设计。分析了CFETR氦冷陶瓷包层放射源项特点,阐述了容器屏蔽厚度的计算模型,使用蒙特卡罗程序MCNP5计算容器表面剂量率。结果表明包装容器表面剂量率与容器厚度之间呈现指数衰减关系。再根据中国现行标准,给出普通碳钢材料和普通碳钢-铅夹层材料两种方案。The shielding design of container of radioactive waste decommissioned from Helium Coolant Ceramic Breeder-Tritium Breeding Blanket(HCCB-TBB) for China Fusion Engineering Testing Reactor(CFETR)is studied. The characteristics of radioactive source term for CFETR HCCB are analyzed, the calculation model of container shielding thickness is focused on, and dose rate of container surface is calculated using MCNP5. It is found that there is an exponential attenuation relationship between the container surface dose rate and the thickness of container. According to the relevant requirements of the current standard of container, two design schemes of container with steel material and steel-lead-steel sandwich material are proposed, respectively.

关 键 词：中国聚变工程实验堆 放射性废物 包装容器 Γ剂量率 屏蔽设计 

分 类 号：TL621[核科学技术—核技术及应用]