微型反应堆乏燃料专用运输容器研制  

Development of Spent Fuel Transport Cask for Miniature Neutron Source Reactor

作　　者：郝倩[1] 李义国[1] 彭旦[1] 王梦娇 鲁谨[1] 洪景彦[1] 吴小波[1] 张金花[1] HAO Qian;LI Yiguo;PENG Dan;WANG Mengjiao;LU Jin;HONG Jingyan;WU Xiaobo;ZHANG Jinhua(China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《机械工程师》2019年第3期35-36,39,共3页Mechanical Engineer

摘　　要：针对微型反应堆乏燃料运输容器设计了专门用于装载微堆乏燃料的组件。容器由屏蔽容器和吊篮组成,外部尺寸为540×831 mm,主要屏蔽材料为铅,主要结构材料为不锈钢。采用ORIGEN2计算最大源强,使用MCNP模拟计算容器表面及距离1 m处剂量率水平。屏蔽实验和实际测量结果表明,容器装载乏燃料时辐射水平小于通常的剂量约束值,也低于GB11806-2004对工作人员的剂量限值,符合微堆乏燃料安全运输的实际需求。Miniature Neutron Source Reactor(MNSR)spent fuel transportation cask designed specifically for loading HEU core is used to ensure spent fuel transport safety in MNSR LEU conversion or decommissioning.MNSR spent fuel transportation cask consists of two parts:the shielding cask and basket.The final design of the cask size isФ540×831 mm.The main structural materials are stainless steel and aluminum alloy,and the main shielding material is lead.ORIGEN2 is used for source term calculation.The dose rates of the cask surface and 1 m away from surface are calculated by MCNP.The shielding experiment and actual measurement results show that the radiation level of the shielding cask when the spent fuel is loaded is less than the usual dose constraint value.The staff radiation level is less than the staff limit dose of GB11806.The results show that MNSR transportation cask can meet the actual needs of safe transportation of miniature reactor spent fuel.

关 键 词：微型反应堆 运输容器 乏燃料 

分 类 号：TL932[核科学技术—辐射防护及环境保护]