4.6 Article

Suggested two layers container for shielding the low and intermediate activity gamma-ray sources

期刊

RADIATION PHYSICS AND CHEMISTRY
卷 199, 期 -, 页码 -

出版社

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.radphyschem.2022.110322

关键词

Gamma-ray sources; Shielding containers; Absorbed dose; Equivalent dose rate; Monte Carlo simulation

资金

  1. Princess Nourah bint Abdulrahman University, Riyadh, Saudi Arabia [PNURSP2022R28]

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Due to the advantages of using gamma-ray radiation sources in various fields, the average equivalent dose received increases. To decrease the equivalent dose, a container made up of metal and glass layers was suggested. The study used simulation code to predict the equivalent dose and confirmed the container's ability to reduce absorbed dose and equivalent dose rate.
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 Cs-137 source with an activity of 3.7E+8 Bq is 26.30 mu Sv/h. This equivalent dose rate from an unprotected source is reduced to 22.75 mu Sv/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 mu Sv/h, raising the WO3. Simultaneously, the equivalent dose rate from an unprotected Co-60 source reaches 50.51 mu Sv/h. It is reduced to 23.56 mu Sv/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.

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