放射性污染金属废物包装容器的屏蔽设计

Shielding design of radioactive contaminated metal waste packaging

针对活度较高的放射性污染金属废物包装容器的屏蔽设计进行了研究。重点阐述了计算废物货包外γ剂量率的圆柱体源模型,推导了圆柱体源剂量场分布的计算公式。通过圆柱体源模型对Ⅷ型钢箱废物货包的计算值与监测数据对比分析,表明圆柱体源模型计算结果能较准确地反映废物货包外γ剂量率分布。基于圆柱体源模型的计算结果,对废物包装容器进行了合理的屏蔽设计,满足了放射性物质运输和处置标准的有关要求。圆柱体源模型对单体货包外剂量率的计算方法简单易实现,而且其计算值比监测值稍大,提供了一定的安全裕度,适合应用于放射性工程实践中。

Focusing on the cylindrical source model to calculate γ dose field of waste packages with the relative formulae then derived. By comparing the calculated data of waste packages of type Ⅷ steel box with the monitoring data, it is found that the cylinder source model could accurately reflect the distributions of γ dose of the waste package. Based on the results of the cylindrical source model,a reasonable shielding technology applicable to waste package containers was designed to meet relevant requirements prescribed in standards about the transport and disposal of radioactive materials. The cylinder source model calculated dose distributions for single package in this paper is simple and easy to implement but slightly larger than the monitoring data providing a certain safety margin for the shielding design. It is suitable for radiological engineering practices.