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Suggested two layers container for shielding the low and intermediate activity gamma-ray sources
Radiation Physics and Chemistry  (IF2.776),  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.