Chemical and radiation shielding effectiveness of some heavy metal oxide glasses for immobilizing radioactive wastes

IF 1.8 4区 材料科学 Q2 MATERIALS SCIENCE, CERAMICS
E. M. Abou Hussein, A. M. Madbouly
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Abstract

Ce/Sb/Mn different borate glass systems based PbO in concentrations of 50, 35, and 15 mol%, respectively, were prepared by the melting–annealing method. Wide chemical, structural, and radiation shielding characterizations were studied before and after 120 kGy of gamma radiation to test the possible use of glasses for immobilizing radioactive wastes. The results showed suitable density values ranging from 3.34 to 5.30 g/cm3 increased by irradiation. FTIR spectra revealed high structural stability against irradiation correlated to the trigonal BO3, tetrahedral BO4 groups, high polarizable Pb2+ ions, and the doped metal ions. Unexpectedly, the chemical durability after in situ leaching process in H2O, 0.1 N HCl, and 0.1 N NaOH for ~ 3 months revealed clear improving after irradiation e.g., enhanced by ~ 25% for Ce-lead borate glass. Scanning electron microscope (SEM) images of the glass surfaces revealed more smooth and homogenous surfaces after irradiation. Shielding parameters by Monte Carlo code (MCNP5) and Phy-X/PSD software were studied, e.g., mass and linear attenuation coefficients (MAC and LAC), effective atomic number (Zeff), radiation protection efficiency (RPE%), half and tenth value layers (HVL and TVL), and heaviness%. Comparing the shielding behavior of the three glasses revealed that Ce-lead borate glass has the highest values of LAC, MAC, Zeff, heaviness%, and RPE% and the lowest values of HVL, TVL, and MFP, referring to the best shielding efficiency. The whole study indicates the desired properties of glasses as immobilizers or containers for radioactive wastes, e.g., nuclear medicine units in hospitals, especially lead borate glass doped Ce ions.

Graphical Abstract

Abstract Image

用于固定放射性废物的一些重金属氧化物玻璃的化学和辐射屏蔽效果
通过熔融-退火法制备了基于氧化铅的 Ce/Sb/Mn 不同硼酸盐玻璃系统,其浓度分别为 50、35 和 15 摩尔%。在伽马辐射 120 kGy 前后,对玻璃的化学、结构和辐射屏蔽特性进行了广泛的研究,以测试其是否可用于固定放射性废料。结果表明,辐照增加了 3.34 至 5.30 克/立方厘米的合适密度值。傅立叶变换红外光谱显示,玻璃在辐照下具有较高的结构稳定性,这与三方 BO3、四面体 BO4 基团、高极化 Pb2+ 离子和掺杂金属离子有关。意想不到的是,在 H2O、0.1 N HCl 和 0.1 N NaOH 中原位浸出约 3 个月后,化学耐久性在辐照后有了明显改善,例如硼酸铅玻璃的化学耐久性提高了约 25%。玻璃表面的扫描电子显微镜(SEM)图像显示,辐照后的玻璃表面更加光滑和均匀。通过蒙特卡洛代码(MCNP5)和 Phy-X/PSD 软件研究了屏蔽参数,如质量和线性衰减系数(MAC 和 LAC)、有效原子序数(Zeff)、辐射防护效率(RPE%)、半值层和十值层(HVL 和 TVL)以及重度%。比较三种玻璃的屏蔽性能发现,硼酸铅玻璃的 LAC、MAC、Zeff、heavyiness% 和 RPE% 值最高,而 HVL、TVL 和 MFP 值最低,屏蔽效率最高。整个研究表明,作为放射性废物的固定器或容器(如医院的核医学装置),玻璃具有理想的特性,特别是掺杂铈离子的硼酸铅玻璃。
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来源期刊
Journal of the Australian Ceramic Society
Journal of the Australian Ceramic Society Materials Science-Materials Chemistry
CiteScore
3.70
自引率
5.30%
发文量
123
期刊介绍: Publishes high quality research and technical papers in all areas of ceramic and related materials Spans the broad and growing fields of ceramic technology, material science and bioceramics Chronicles new advances in ceramic materials, manufacturing processes and applications Journal of the Australian Ceramic Society since 1965 Professional language editing service is available through our affiliates Nature Research Editing Service and American Journal Experts at the author''s cost and does not guarantee that the manuscript will be reviewed or accepted
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