60Co放射源运输容器屏蔽性能检测

Shielding Performance Measurements on Container for 60Co Radioactive Sources Transport

  • 摘要: 工业及医疗用放射源主要包括60Co、137Cs、131I、32P、153Sm、99Mo、90Sr、89Sr等核素,射线形式有α、β、γ、中子等。本文针对运输活动中γ辐射,使用现有的60Co放射源运输容器,开展辐射屏蔽性能检测技术研究。通过模拟计算和实验测量,得到运输容器最大装载活动情况下外部辐射水平,并对计算和实验结果进行了比较。针对放射源在屏蔽容器中安放位置发生偏移和放射源在容器中安放方式不同对容器外部的辐射水平影响进行了相关研究。研究结果可对今后完善放射性物质运输容器的辐射屏蔽性能检测提供一定的借鉴。

     

    Abstract: Some radioactive sources are often used in irradiation industry and radiotherapy, such as 60Co, 137Cs, 131I, 32P, 153Sm, 99Mo, 90Sr, 89Sr and so on. The radiation include α、β、γ and n. The radiation from γ sources are the mostly concerned during the transporting of radioactive sources. The shielding performance measurements on container for 60Co radioactive sources transport were discussed by using both Monte Carlo method simulation calculation and experiment measurement. Some important factors was discussed which could affect the results of shielding performance measurements. The layout of radioactive sources had a important impact on the monitoring results of the external radiation levels of radiation sources transport container. The results afforded the contribution to the improvement of the radiation monitoring and management of radioactive material transportation package.

     

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