300#反应堆乏燃料元件转运屏蔽吊筒的放射性屏蔽校核计算  

Verifying calculation of the radioactive shielding of the cylindrical canister designed to convey SPRR-300 spent fuel assemblies

作　　者：杨锐[1] 陈炜[1] 

机构地区：[1]中国工程物理研究院核物理与化学研究所

出　　处：《核电子学与探测技术》2004年第6期790-792,共3页Nuclear Electronics & Detection Technology

摘　　要：介绍了根据300#堆乏燃料元件组件的实测剂量数据,对初步设计的乏燃料元件转运屏蔽吊筒的放射性屏蔽进行的详细校核计算。给出了乏燃料元件屏蔽前后不同距离处的剂量率。计算结果与实际验证表明屏蔽吊筒所选取的屏蔽厚度是合适的。The paper presented the detailed calculation of the radioactive shielIn the cylindrical canister designed to convey SPRR-300 spent fuel assemblies on the basis of their actual measurements, with the dose rates are given at different intervals for shielded and unshielded spent fuel assemblies. The appropriateness of the thickness of the canister is shown by the calculation, along with the experimental operation is followed.

关 键 词：乏燃料元件 转运屏蔽吊筒 校核计算 300#反应堆 

分 类 号：TL352[核科学技术—核技术及应用]