Enhancing mechanical properties and radiation shielding of high-strength concrete with bulk lead oxide and granodiorite

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-10-10 DOI:10.1016/j.nucengdes.2024.113626

Islam N. Fathy , Alaa A. El-Sayed , Maged E. Elfakharany , Alaa A. Mahmoud , Mohamed A. Abouelnour , Abdelhalim S. Mahmoud , Islam M. Nabil

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引用次数: 0

Abstract

This paper evaluates the influence of bulk lead oxide (PbO) and granodiorite (GD) powders, individually and in combination at optimal replacement ratios, on the setting time, workability, compressive strength, and radiation attenuation properties of high-strength concrete (HSC). Twelve HSC mixes were prepared: a control mix, five mixes containing varying percentages of PbO, five mixes containing varying percentages of GD, and one hybrid mix combining 5 % PbO and 7 % GD. The optimal replacement ratio 7 % with GD powder increased the compressive strength of the concrete by 19.1 %. A comprehensive microstructural and compositional analysis of XBL/G-concrete was conducted employing X-ray Fluorescence (XRF), X-ray Diffraction analysis (XRD), Transmission Electron Microscopy (TEM) and Energy Dispersive X-ray (EDX) techniques. Radiation shielding effectiveness was evaluated using Phy-X software and Monte Carlo-5 simulations (MCS), focusing on γ-rays and fast neutrons. 2 % replacement of PbO enhanced the compressive strength of the concrete. However, increasing the PbO content to 5 % resulted in an 8.57 % reduction in strength compared to the control mix. The hybrid concrete mix of 5 % PbO and 7 % GD demonstrated superior radiation shielding capabilities in terms of linear/mass attenuation, with a 3.12 % increase in compressive strength relative to the control sample. The combined concrete sample of 5 % PbO and 7 % GD were higher than the samples mixed with GD and lower than the samples mixed with PbO of concentrations 3, 4, and 5 % in terms of the linear/mass attenuation. The linear attenuation’s order of the XBL/G-concrete samples was: 1BG < 3BG < 5BG < 7BG < 9BG < 1BL < 2BL < 5BLG7 < 3BL < 4BL < 5BL. Also, the mixed concretes of 5 % PbO and 7 % GD demonstrated a superior from fast neutron shielding capabilities. The tested XBL/G-concrete samples provide adequate protection against γ-rays and fast neutrons for nuclear and medical facilities shield radiation.

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用大块氧化铅和花岗闪长岩提高高强度混凝土的力学性能和辐射屏蔽性能

本文评估了大块氧化铅（PbO）粉末和花岗闪长岩（GD）粉末以最佳替代比例单独或混合使用对高强度混凝土（HSC）的凝结时间、工作性、抗压强度和辐射衰减性能的影响。我们制备了 12 种高强度混凝土混合料：一种对照混合料、五种含有不同比例氧化铅的混合料、五种含有不同比例广东十一选五粉的混合料，以及一种结合了 5 % 氧化铅和 7 % 广东十一选五粉的混合料。GD 粉的最佳替代率为 7%，使混凝土的抗压强度提高了 19.1%。利用 X 射线荧光 (XRF)、X 射线衍射分析 (XRD)、透射电子显微镜 (TEM) 和能量色散 X 射线 (EDX) 技术对 XBL/G 混凝土进行了全面的微观结构和成分分析。使用 Phy-X 软件和蒙特卡罗-5 模拟 (MCS) 评估了辐射屏蔽效果，重点是 γ 射线和快中子。氧化铅的 2% 取代量提高了混凝土的抗压强度。然而，与对照组相比，将氧化铅含量提高到 5% 会导致强度降低 8.57%。含 5% PbO 和 7% GD 的混合混凝土在线性/质量衰减方面表现出更出色的辐射屏蔽能力，抗压强度比对照样本提高了 3.12%。就线性/质量衰减而言，5% PbO 和 7% GD 混合混凝土样品高于掺有 GD 的样品，低于掺有浓度为 3%、4% 和 5%的 PbO 的样品。XBL/G 混凝土样品的线性衰减顺序为：1BG < 3BG < 5BG < 7BG < 9BG < 1BL < 2BL < 5BLG7 < 3BL < 4BL < 5BL。此外，5% PbO 和 7% GD 混合混凝土的快中子屏蔽能力更强。经测试的 XBL/G 混凝土样品可为核和医疗设施屏蔽辐射提供足够的γ射线和快中子防护。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.