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Preparation and radiation shielding features of high density, transparent borosilicate glasses with different Bi2O3 contents

Sayyed M.I.|Rashad M.|More Chaitali V.|Kumar Anjan
한국원자력학회 (Korean Nuclear Society)|2024.12|Nuclear Engineering and Technology|제56권 제12호|pp. 5043-5047|DOI 10.1016/j.net.2024.07.013

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키워드

Shielding propertiesRadiological parametersBismuth borosilicate glassesPhy-X/PSD
주제분류원자력공학

초록

This work assessed highly effective bismuth borosilicate glasses’ nuclear radiation shielding capabilities in terms of different concentrations of Bi2O3. Melt-quenching was the method used to create the glasses. The Phy-X/PSD program was used to compute the μm values. The bismuth borosilicate glasses’ nuclear radiation shielding properties were determined in the 0.015–15 MeV energy range. Increasing Bi₂O₃ concentration resulted in an increase in mass attenuation coefficient, linear attenuation coefficient, and effective atomic number. Conversely, the half value layer and mean free path values decreased. The B48Bi17 sample, with its largest Zeff, is a great gamma attenuator. The results of a new study may help to clarify the nature of the Bi2O3 additive used in borosilicate glasses, which are a potential form of shield for use in industrial and medical radiation facilities.

Abstract

This work assessed highly effective bismuth borosilicate glasses’ nuclear radiation shielding capabilities in terms of different concentrations of Bi2O3. Melt-quenching was the method used to create the glasses. The Phy-X/PSD program was used to compute the μm values. The bismuth borosilicate glasses’ nuclear radiation shielding properties were determined in the 0.015–15 MeV energy range. Increasing Bi₂O₃ concentration resulted in an increase in mass attenuation coefficient, linear attenuation coefficient, and effective atomic number. Conversely, the half value layer and mean free path values decreased. The B48Bi17 sample, with its largest Zeff, is a great gamma attenuator. The results of a new study may help to clarify the nature of the Bi2O3 additive used in borosilicate glasses, which are a potential form of shield for use in industrial and medical radiation facilities.

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관련 논문AI추천

A closer look at the structure and gamma-ray shielding properties of newly designed boro -tellurite glasses reinforced by bismuth (III) oxideAbdullahi I., Hashim S., Ismail Abd Khamim, Mahmoud K.G., Sayyed M.I., Thabit Hammam Abdurabu, Yusof N.N.한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제5호Bi2O3 additive effects on gamma radiation shielding properties of 45SiO2-20B2O3-23Na2O3-9CaO-3Al2O3 glassJavid Ghezelgechi Hossein, Rezvani Mohammad한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제8호Impact of varying Bi2O3 content on physical, mechanical, structural and gamma ray shielding properties of Bi2O3-B2O3-SiO2-Na2O glass systemAlmuqrin Aljawhara H., Kumar Ashok, Sayyed M.I.한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제10호Understanding radiation shielding performance through a comparative study of half value layer in novel and preexisting silicate glassesAlbarzan B., Almuqrin Aljawhara H., Alrowaily Albandari.W., Sayyed M.I.한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제3호Unveiling the potential of Nd2O3 in optimizing the radiation shielding performance of B2O3–TiO2–BaO–ZnO-Nd2O3 glassesAlbarzan B., Alharbi F.F., Al Huwayz Maryam, Almuqrin Aljawhara H., Sayyed M.I.한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제1호Study the impact of MgO, Al2O3, MoO3, BaO, ZnO and PbO on the radiation shielding performance of borate glassesElsafi M., Hedaya A.M., Sayyed M.I.한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제7호

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