王智鹏,荣誉,王鹏毅,王长武,孙谦,张煜航,郝嘉欣,李俊,孙树堂.放射性物品运输容器屏蔽性能评价方法及实践[J].包装工程,2024,45(23):311-317.
WANG Zhipeng,RONG Yu,WANG Pengyi,WANG Changwu,SUN Qian,ZHANG Yuhang,HAO Jiaxin,LI Jun,SUN Shutang.Evaluation Method and Practice of Shielding Performance of Radioactive Material Transport Container[J].Packaging Engineering,2024,45(23):311-317. |
| 放射性物品运输容器屏蔽性能评价方法及实践 |
| Evaluation Method and Practice of Shielding Performance of Radioactive Material Transport Container |
| 投稿时间：2024-08-28 |
| DOI：10.19554/j.cnki.1001-3563.2024.23.034 |
| 中文关键词: 放射性物品运输容器 屏蔽性能 蒙特卡洛软件计算 屏蔽试验 |
| 英文关键词: radioactive material transport container shielding performance Monte Carlo software calculation shielding test |
| 基金项目: |
|
| 摘要点击次数: |
| 全文下载次数: |
| 中文摘要: |
| 目的 为放射性物品运输容器的屏蔽性能评价工作提供参考和建议。方法 以1种典型大容量厚屏蔽放射源运输容器作为研究对象，使用辐射防护领域常用的3种屏蔽评价方法(公式计算、蒙特卡洛软件计算、屏蔽试验)对其进行屏蔽性能评价，给出相同活度的60Co放射源在运输容器外部指定位置产生的辐射水平。使用60Co放射源(12 000 Ci)和辐射测量仪器对研究对象直接开展屏蔽性能检测试验，并通过换算给出在装载指定活度60Co放射源时的外部辐射水平，并将实测结果与计算结果进行对比分析。结果 使用3种不同方法得到了同一运输容器在装载相同内容物时其外部指定位置的辐射水平。使用公式计算最为方便快捷;使用蒙特卡洛软件计算得到的结果和实测结果更为接近;使用放射源直接开展测量获得的结果最为直观和可信，但受测量环境和仪器影响较大。结论 3种计算方法和实测结果在数值上略有不同，但均位于同一数量级，均可用于放射性物品运输容器的屏蔽性能评价。 |
| 英文摘要: |
| The work aims to provide reference and suggestions for shielding performance evaluation of radioactive material transport container. With a typical large-capacity radioactive source transport container as the research object, 3 shielding evaluation methods (formula calculation, Monte Carlo software calculation and shielding test) commonly used in radioactive protection were employed to evaluate the shielding performance of the container and the radiation dose rate generated by the 60Co radioactive source (12 000 Ci) of the same activity at the designated location outside the container was given. The 60Co radioactive source (12 000 Ci) and the radiation measuring instrument were used to directly test the shielding performance of the research object, and the external radiation level when the specified 60Co radioactive source was loaded was obtained through conversion, and the measured results were compared with the calculated results. 3 different methods were used to obtain the radiation level at a specified location outside the same transport container loaded with the same contents. Formula calculation was the most convenient and fast. The results calculated by Monte Carlo software were closer to the measured results. The results obtained by direct measurement with radioactive sources were the most intuitive and reliable, but were greatly affected by the measuring environment and instruments. The results obtained by 3 calculation methods and the measured results are slightly different in numerical value, but they are all in the same order of magnitude and can be used to evaluate the shielding performance of the radioactive material transport container. |
|
查看全文
查看/发表评论 下载PDF阅读器 |
| 关闭 |
|
|
|
渝公网安备 50010702501716号