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Suggested two layers container for shielding the low and intermediate activity gamma-ray sources
Radiation Physics and Chemistry ( IF 2.9 ) Pub Date : 2022-06-21 , DOI: 10.1016/j.radphyschem.2022.110322
Hanan Al-Ghamdi , O.L. Tashlykov , M.I. Sayyed , Aljawhara A.H. Almuqrin , Mayeen Uddin Khandaker , K.A. Mahmoud

Due to the advantages of using gamma-ray radiation sources in various fields, the average equivalent dose received due to the exposure to these sources increases. The wrong handling or direct exposure to these sources give raises the equivalent dose for the receiver. Thus, a container made up of two layers (metal and glass layers) was suggested to decrease the recorded equivalent dose received from the gamma-ray radioactive sources to an acceptable limit. The Monte Carlo MCNP simulation code was utilized to predict the equivalent dose around the container's outer surface and at 100 cm from the center of the outer container's faces. For example, the simulation study illustrated that the equivalent dose rate received at 100 cm from an unprotected 137Cs source with an activity of 3.7E+8 Bq is 26.30 μSv/h. This equivalent dose rate from an unprotected source is reduced to 22.75 μSv/h using the inner layer of the stainless steel with a thickness of 0.5 cm. After that, the equivalent dose rate reduced from 22.75 to 7.60 μSv/h, raising the WO3. Simultaneously, the equivalent dose rate from an unprotected Co-60 source reaches 50.51 μSv/h. It is reduced to 23.56 μSv/h by using a container consisting of an inner layer of stainless steel with a thickness of 0.5 cm and an outer glass layer of BaWP7 glass sample with WO3 content of 60 mol % and thickness of 5 cm.

The present study showed the suggested container's ability in reducing the absorbed dose and equivalent dose rate for intermediate activity gamma-ray sources used in laboratories and nuclear medicine.



中文翻译:

建议的两层容器,用于屏蔽中低活度伽马射线源

由于在各个领域使用伽马射线辐射源的优势,由于暴露于这些源而获得的平均等效剂量增加。错误处理或直接暴露于这些源会增加接收者的等效剂量。因此,建议使用由两层(金属层和玻璃层)组成的容器,以将从伽马射线放射源接收的记录当量剂量降低到可接受的限度。Monte Carlo MCNP 模拟代码用于预测容器外表面周围和距容器外表面中心 100 厘米处的等效剂量。例如,模拟研究表明,在 100 厘米处从未受保护的137活性为 3.7E+8 Bq 的 Cs 源为 26.30 μSv/h。使用厚度为 0.5 cm 的不锈钢内层,来自未受保护源的等效剂量率降低到 22.75 μSv/h。之后,等效剂量率从22.75降低到7.60 μSv/h,提高了WO 3。同时,未受保护的 Co-60 源的等效剂量率达到 50.51 μSv/h。通过使用由内层厚度为 0.5 cm 的不锈钢和外层玻璃层为 WO 3含量为 60 mol%、厚度为 5 cm 的 BaWP7 玻璃样品组成的容器,将其降低到 23.56 μSv/h。

本研究表明,建议的容器能够降低实验室和核医学中使用的中等活动伽马射线源的吸收剂量和等效剂量率。

更新日期:2022-06-26
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