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A closer look at the structure and gamma-ray shielding properties of newly designed boro -tellurite glasses reinforced by bismuth (III) oxide

Sayyed M.I.|Thabit Hammam Abdurabu|Ismail Abd Khamim|Yusof N.N.|Mahmoud K.G.|Abdullahi I.|Hashim S.
한국원자력학회 (Korean Nuclear Society)|2023.05|Nuclear Engineering and Technology|제55권 제5호|pp. 1734-1741|DOI 10.1016/j.net.2022.12.036

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키워드

Radiation shieldingMonte Carlo simulationBoro-tellurite glassBismuth (III) 0xide
주제분류원자력공학

초록

This work presents the synthesis and preparation of a new glass system described by the equation of (70- x) B2O3e5TeO2 e20SrCO3e5ZnO exBi2O3, x ¼ 0, 1, 5, 10, and 15 mol. %, using the melt quenching technique at a melting temperature of 1100 C. The photon-shielding characteristics mainly the linear attenuation coefficient (LAC) of the prepared glass samples were evaluated using Monte Carlo (MC) simulation N-particle transport code (MCNP-5) at gamma-ray energy extended from 59 keV to 1408 keV emitted by the radioisotopes Am-241, Ba-133, Cs-137, Co-60, Na-22, and Eu-152. Furthermore, we observed that the Bi2O3 content of the glasses had a significantly stronger impact on the LAC at 59 and 356 keV. The study of the lead equivalent thickness shows that the performance of fabricated glass sample with 15 mol.% of Bi2O3 is four times less than the performance of pure lead at low gamma photon energy while it is enhanced and became two times lower the perforce of pure lead at high energy. Therefore, the fabricated glasses special sample with 15 mol.% of Bi2O3 has good shielding properties in low, intermediate, and high energy intervals

Abstract

This work presents the synthesis and preparation of a new glass system described by the equation of (70- x) B2O3e5TeO2 e20SrCO3e5ZnO exBi2O3, x ¼ 0, 1, 5, 10, and 15 mol. %, using the melt quenching technique at a melting temperature of 1100 C. The photon-shielding characteristics mainly the linear attenuation coefficient (LAC) of the prepared glass samples were evaluated using Monte Carlo (MC) simulation N-particle transport code (MCNP-5) at gamma-ray energy extended from 59 keV to 1408 keV emitted by the radioisotopes Am-241, Ba-133, Cs-137, Co-60, Na-22, and Eu-152. Furthermore, we observed that the Bi2O3 content of the glasses had a significantly stronger impact on the LAC at 59 and 356 keV. The study of the lead equivalent thickness shows that the performance of fabricated glass sample with 15 mol.% of Bi2O3 is four times less than the performance of pure lead at low gamma photon energy while it is enhanced and became two times lower the perforce of pure lead at high energy. Therefore, the fabricated glasses special sample with 15 mol.% of Bi2O3 has good shielding properties in low, intermediate, and high energy intervals

참고문헌 (41)

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관련 논문AI추천

Preparation and radiation shielding features of high density, transparent borosilicate glasses with different Bi2O3 contentsKumar Anjan, More Chaitali V., Rashad M., Sayyed M.I.한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제12호Bi2O3 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 제10호Influence of transition metals on the radiation shielding capability of Eu3+ ions doped telluro borophosphate glassesBassam S.A., El-Rehim A.F. Abd, Khandaker Mayeen Uddin, Mahmoud K.A., Naseer K.A., Sangeeth C.S. Suchand, Sayyed M.I.한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제3호A new protective glass material against gamma ray: Thorough analysis to determine the impact of adding gadolinium (III) oxideHanafy Taha A., Mahmoud K.A., Sayyed M.I.한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제1호Optical, thermal and gamma ray attenuation characteristics of tungsten oxide modified: B2O3–SrCO3–TeO2–ZnO glass seriesAbdullahi I., Elsafi Mohamed, Hashim S., Ismail Abd Khamim, Jagannath G., Keshavamurthy K., Sayyed M.I., Thabit Hammam Abdurabu한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제1호

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