Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability
The gamma-ray shielding ability of various Bentonite–Cement mixed materials from northeast Egypt have been examined by determining their theoretical and experimental mass attenuation coefficients, μ<sub>m</sub> (cm<sup>2</sup>g<sup>−1</sup>), at photon energies of...
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author | Ahmed M. El-Khatib Mohamed Elsafi Mohamed N. Almutiri R. M. M. Mahmoud Jamila S. Alzahrani M. I. Sayyed Mahmoud I. Abbas |
author_facet | Ahmed M. El-Khatib Mohamed Elsafi Mohamed N. Almutiri R. M. M. Mahmoud Jamila S. Alzahrani M. I. Sayyed Mahmoud I. Abbas |
author_sort | Ahmed M. El-Khatib |
collection | DOAJ |
description | The gamma-ray shielding ability of various Bentonite–Cement mixed materials from northeast Egypt have been examined by determining their theoretical and experimental mass attenuation coefficients, μ<sub>m</sub> (cm<sup>2</sup>g<sup>−1</sup>), at photon energies of 59.6, 121.78, 344.28, 661.66, 964.13, 1173.23, 1332.5 and 1408.01 keV emitted from <sup>241</sup>Am, <sup>137</sup>Cs, <sup>152</sup>Eu and <sup>60</sup>Co point sources. The μ<sub>m</sub> was theoretically calculated using the chemical compositions obtained by Energy Dispersive X-ray Analysis (EDX), while a NaI (Tl) scintillation detector was used to experimentally determine the μ<sub>m</sub> (cm<sup>2</sup>g<sup>−1</sup>) of the mixed samples. The theoretical values are in acceptable agreement with the experimental calculations of the XCom software. The linear attenuation coefficient (μ), mean free path (MFP), half-value layer (HVL) and the exposure buildup factor (EBF) were also calculated by knowing the μ<sub>m</sub> values of the examined samples. The gamma-radiation shielding ability of the selected Bentonite–Cement mixed samples have been studied against other puplished shielding materials. Knowledge of various factors such as thermo-chemical stability, availability and water holding capacity of the bentonite–cement mixed samples can be analyzed to determine the effectiveness of the materials to shield gamma rays. |
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issn | 1996-1944 |
language | English |
last_indexed | 2024-03-10T08:37:59Z |
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spelling | doaj.art-4e31106d245f4783a74f63d905dbbd802023-11-22T08:31:34ZengMDPI AGMaterials1996-19442021-08-011416469710.3390/ma14164697Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding CapabilityAhmed M. El-Khatib0Mohamed Elsafi1Mohamed N. Almutiri2R. M. M. Mahmoud3Jamila S. Alzahrani4M. I. Sayyed5Mahmoud I. Abbas6Physics Department, Faculty of Science, Alexandria University, Alexandria 21511, EgyptPhysics Department, Faculty of Science, Alexandria University, Alexandria 21511, EgyptPhysics Department, Faculty of Science, Alexandria University, Alexandria 21511, EgyptRadiation Protection Department, Nuclear and Radiation Safety Research Center, Atomic Energy Authority, Cairo 11762, EgyptPhyscis Department, College of Science, Princess Nourah Bint Abdulrahman University, Riyadh 11671, Saudi ArabiaDepartment of Physics, Faculty of Science, Isra University, Amman 11622, JordanPhysics Department, Faculty of Science, Alexandria University, Alexandria 21511, EgyptThe gamma-ray shielding ability of various Bentonite–Cement mixed materials from northeast Egypt have been examined by determining their theoretical and experimental mass attenuation coefficients, μ<sub>m</sub> (cm<sup>2</sup>g<sup>−1</sup>), at photon energies of 59.6, 121.78, 344.28, 661.66, 964.13, 1173.23, 1332.5 and 1408.01 keV emitted from <sup>241</sup>Am, <sup>137</sup>Cs, <sup>152</sup>Eu and <sup>60</sup>Co point sources. The μ<sub>m</sub> was theoretically calculated using the chemical compositions obtained by Energy Dispersive X-ray Analysis (EDX), while a NaI (Tl) scintillation detector was used to experimentally determine the μ<sub>m</sub> (cm<sup>2</sup>g<sup>−1</sup>) of the mixed samples. The theoretical values are in acceptable agreement with the experimental calculations of the XCom software. The linear attenuation coefficient (μ), mean free path (MFP), half-value layer (HVL) and the exposure buildup factor (EBF) were also calculated by knowing the μ<sub>m</sub> values of the examined samples. The gamma-radiation shielding ability of the selected Bentonite–Cement mixed samples have been studied against other puplished shielding materials. Knowledge of various factors such as thermo-chemical stability, availability and water holding capacity of the bentonite–cement mixed samples can be analyzed to determine the effectiveness of the materials to shield gamma rays.https://www.mdpi.com/1996-1944/14/16/4697bentonite–cement mixed materialsMFPXCom softwaremass attenuation coefficient |
spellingShingle | Ahmed M. El-Khatib Mohamed Elsafi Mohamed N. Almutiri R. M. M. Mahmoud Jamila S. Alzahrani M. I. Sayyed Mahmoud I. Abbas Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability Materials bentonite–cement mixed materials MFP XCom software mass attenuation coefficient |
title | Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability |
title_full | Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability |
title_fullStr | Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability |
title_full_unstemmed | Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability |
title_short | Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability |
title_sort | enhancement of bentonite materials with cement for gamma ray shielding capability |
topic | bentonite–cement mixed materials MFP XCom software mass attenuation coefficient |
url | https://www.mdpi.com/1996-1944/14/16/4697 |
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