废玻璃对混凝土伽马射线屏蔽性能的影响

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-23 DOI:10.1016/j.anucene.2024.110876
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引用次数: 0

摘要

在这项工作中,我们将尼日利亚当地的低成本材料结合在一起,生产出一种可用于屏蔽电离γ射线的无铅混凝土。这项工作研究了用碎废玻璃部分替代粗骨料(碎花岗岩)对化学、物理和辐射屏蔽特性的影响。实验测量了所开发混凝土的密度,并利用连接到 ARL-QUANT'X-EDXRF 分析仪的 Thermo-Scientific X 射线荧光仪测定了所制造混凝土的元素化学成分。废玻璃/花岗岩(WG/G)替代率在 0% 到 17.6% 之间的增加会降低混凝土的密度,从 2.4 g/cm3 降至 2.33 g/cm3。另一方面,随着 WG/G 比率的提高,生产出的混凝土的单位质量吸水率(MAC)也随之增加,在 0.081 MeV 时,WG/G 比率在 0 到 17.6 % 之间时,单位质量吸水率增加了 0.217-0.247 cm2/g。同时,研究表明,对于 WG/G 含量依次为 0.0%、5.3%、11.1% 和 17.6%的混凝土,在 2.506 MeV 时,10 厘米厚的混凝土的辐射防护效率(RPE)分别达到 53.49%、61.14%、54.98% 和 55.29%。因此,开发的混凝土厚度越厚,屏蔽能力越强,可用于辐射防护应用。
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Influence of waste glass on the gamma-ray shielding performance of concrete

In this work, the local low-cost materials from Nigeria were companied together to produce a lead-free concrete that can be used in shielding the ionizing γ-rays. This work investigated the impacts of partially replacing coarse aggregates (crushed granite) with a crushed waste glass on the chemical, physical, and radiation shielding characteristics. The developed concretes’ density was measured experimentally, and the fabricated concretes’ elemental chemical composition was determined utilizing a Thermo-Scientific X-ray fluorescence connected to an ARL-QUANT’X-EDXRF-Analyzer. The increase in the waste glass/granite (WG/G) substitution ratio between 0 and 17.6 % decreases the density of the produced concrete from 2.4 g/cm3 to 2.33 g/cm3. On the other hand, the absorption per unit mass (MAC) of the produced concretes increased by raising the WG/G ratio, where there was a 0.217–0.247 cm2/g increase in the MAC at 0.081 MeV, by raising the WG/G ratio between 0 and 17.6 %. Simultaneously, the study shows that the radiation protection efficiency (RPE) at 2.506 MeV for a 10 cm thickness of the fabricated concrete reaches 53.49, 61.14, 54.98, and 55.29 % for concretes with WG/G content of 0.0, 5.3, 11.1, and 17.6 % with the same order, respectively. Therefore, the thicker thicknesses of the developed concretes can offer high shielding capacity to be applied in radiation protection applications.

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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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