采用新型抹灰技术的可持续混凝土的辐射屏蔽性能

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mohamed A.E.M. Ali , Mohammed A.Y. Hafez , Nabil M. Nagy , Neveen S. Abed
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引用次数: 0

摘要

在混凝土应用中。这类混凝土的主要/关键应用是辐射屏蔽设施。钢渣和硅灰都是可用作骨料和水泥替代物的常见副产品材料。因此,在这项研究工作中,除了硅灰之外,钢渣还被用作混凝土生产中的重集料,以提供可能具有更好辐射屏蔽性能的可持续混凝土混合物。在进行的可持续混凝土混合物上使用了不同的水泥基抹灰,除了纳米二氧化钛作为砂的完全替代物外,还使用了不同的粉末材料:赤铁矿、磁铁矿、重晶石、膨润土和钢渣粉。对提出的灰泥进行了介绍,以确定在静态性能和对伽马射线和中子辐射的衰减能力方面的最佳灰泥技术。结果表明,与传统混凝土相比,在混凝土混合物中使用钢渣和硅灰可提高抗压强度达 9.09%,而在传统抹灰中添加纳米钛可提高抗压强度达 38.65%。相反,用上述粉末状材料完全取代传统硅砂后,水泥基抹灰的抗压强度普遍降低了 30.83%。不过,对 Cs-137 和 Co-60 能量的辐射屏蔽性能分别提高了 20% 和 26%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Radiation shielding properties of sustainable concrete with novel plastering techniques
In concrete applications. Major/critical applications of such concrete are radiation-shielding facilities. Both steel slag and silica fume are examples of common by-product materials that can be used as a replacer of aggregates and cement. Thus, in this research work, steel slag was utilized as heavy aggregate in concrete production besides silica fume to present sustainable concrete mixtures probably with better radiation-shielding properties. Different cementitious plasters were applied on the conducted sustainable concrete mixture using different powdery materials; hematite, magnetite, barite, bentonite, and steel slag powders in addition to nano-titanium dioxide as full replacers for sand. The proposed plasters were presented to determine the optimum plaster technique in terms of static performance and attenuation capability against gamma and neutron radiations. The results exhibited that utilizing steel slag and silica fume in concrete mixtures enhanced compressive strength by up to 9.09 % compared to conventional concrete, while the addition of nano-titanium to conventional plaster led to superior enhancement in the compressive strength by up to 38.65 % relative to traditional plaster. Conversely, fully replacing conventional silica sand with the abovementioned powdery materials generally reduced the compressive strength of cementitious plasters by up to 30.83 %. However, the radiation shielding properties against Cs-137, and Co-60 energies have been enhanced by up to 20 % and 26 %, respectively.
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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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