Investigation of optical and radiation shielding characteristics of Gd2O3-doped tellurium zinc borate glass via melt-quenching method

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-02-19 DOI:10.1016/j.anucene.2025.111262

S.N. Nazrin , Seema Thakur , Camellia Doroody , Halimah Badioze Zaman , Siti Nur Aida Mohd Nashruddin , Mongi Amami , Faznny Mohd Fudzi

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Abstract

The melt-quenching approach was used to produce Gd₂O₃-doped tellurium zinc borate glass system with composition {[(TeO₂)_0.7(B₂O₃)_0.3]_0.7(ZnO)_0.3}₁₋_x(Gd₂O₃)_x where x = 0.01, 0.02, 0.03, 0.04 as well as 0.05 M fraction and assess its optical and radiation shielding characteristics. Phy-X/PSD software was used to calculate parameters such as mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half value layer (HVL), tenth value layer (TVL), and mean free path (MFP) in order to evaluate the effectiveness of radiation shielding. Glass containing 0.05 M fraction of Gd₂O₃exhibited the greatest shielding efficacy, surpassing conventional concretes such as chromite and serpentine. The refractive index dropped from 2.518 to 2.352 while the direct and indirect optical band gaps increased from 3.239 to 3.519 eV and from 2.587 to 3.172 eV, respectively. The amorphous nature of the glass was validated by XRD, while TeO₃, TeO₄, BO₃, and BO₄ vibrational groups were identified by infrared spectra demonstrating the potential of the prepared glass for optical and radiation shielding applications.

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采用熔淬法制备了掺杂 Gd2O3 的硼酸碲锌玻璃体系，其组成为 {[(TeO2)0.7(B2O3)0.3]0.7(ZnO)0.3}1-x(Gd2O3)x 其中 x = 0.01、0.02、0.03、0.04 以及 0.05 M 分数，并对其光学和辐射屏蔽特性进行了评估。使用 Phy-X/PSD 软件计算质量衰减系数 (MAC)、线性衰减系数 (LAC)、半值层 (HVL)、十值层 (TVL) 和平均自由路径 (MFP) 等参数，以评估辐射屏蔽的有效性。含 0.05 M 分量 Gd2O3 的玻璃显示出最大的屏蔽效果，超过了铬铁矿和蛇纹石等传统混凝土。折射率从 2.518 降至 2.352，直接和间接光带隙分别从 3.239 eV 和 2.587 eV 增至 3.519 eV 和 3.172 eV。XRD 验证了这种玻璃的非晶性质，而红外光谱则确定了 TeO3、TeO4、BO3 和 BO4 的振动基团，这表明制备的玻璃具有光学和辐射屏蔽应用的潜力。

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来源期刊

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.