A new approach toward enhancing the gamma-ray shielding efficiency: Zn ions effects on synthesized B2O3-PbO-BaO toward gamma-ray protection applications

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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Abstract

In the present work, a newly produced PbO-BaO-B2O3 glass system’s mechanical, physical, and radiation absorption capabilities were studied to determine the effectivity of B2O3 substitution by ZnO. The melt-quench process produced the glasses utilized in the present investigation. The melting point used was 1000 °C, and the temperature at which they were annealed was 400 °C. The experimental measurement of the density for manufactured glass samples was conducted using Archimedes’ theory. It was observed that all density values of the fabricated glasses were raised when the concentration of ZnO was increased from 0 to 20 mol.%. Based on the model proposed by Makishima and Mackenzie from Young, bulk, shear, and longitudinal moduli, it was observed that there was a decrease as the concentration of ZnO was increased in the manufactured glasses. Microhardness was found to be reduced from 4.692 GPa to 4.218 GPa, while the Poisson ratio was found to be decreased from 0.234 to 0.229 when the percentage of ZnO was raised from 0 to 20 mol.%. In contrast, the assessment of radiation shielding qualities through the utilization of Monte Carlo software simulation demonstrates an augmentation in the radiation absorption capability of the manufactured glass samples due to the exchange between B2O3 and ZnO compounds. We used the MCNP5 code to study the radiation shielding properties in a wide energy range of 0.03–2.605 MeV. The linear attenuation coefficient LAC of the produced glass samples increased from 0.315 cm−1 to 0.369 cm−1 when the ZnO concentrations were enriched from 0 to 20 mol.%, respectively.

提高伽马射线屏蔽效率的新方法:锌离子对合成 B2O3-PbO-BaO 在伽马射线防护应用中的影响
在本研究中,对新生产的 PbO-BaO-B2O3 玻璃体系的机械、物理和辐射吸收能力进行了研究,以确定氧化锌替代 B2O3 的效果。本研究采用熔融-淬火工艺生产玻璃。熔点为 1000 °C,退火温度为 400 °C。利用阿基米德理论对制造的玻璃样品的密度进行了实验测量。结果表明,当氧化锌的浓度从 0 摩尔% 增加到 20 摩尔% 时,所制造玻璃的所有密度值都有所提高。根据 Makishima 和 Mackenzie 从杨氏模量、体积模量、剪切模量和纵向模量提出的模型,观察到随着制造的玻璃中氧化锌浓度的增加,玻璃的杨氏模量、体积模量、剪切模量和纵向模量都有所下降。当氧化锌的百分比从 0 摩尔%提高到 20 摩尔%时,微硬度从 4.692 GPa 降至 4.218 GPa,泊松比从 0.234 降至 0.229。相反,通过蒙特卡洛软件模拟对辐射屏蔽质量的评估表明,由于 B2O3 和 ZnO 化合物之间的交换,制造的玻璃样品的辐射吸收能力得到了提高。我们使用 MCNP5 代码研究了 0.03-2.605 MeV 宽能量范围内的辐射屏蔽特性。当氧化锌的浓度从 0 摩尔% 增加到 20 摩尔% 时,玻璃样品的线性衰减系数 LAC 分别从 0.315 厘米-1 增加到 0.369 厘米-1。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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