The impact of pressure rate on the physical, structural and gamma-ray shielding capabilities of novel light-weight clay bricks

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Technology Pub Date : 2024-09-19 DOI:10.1016/j.net.2024.09.022
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Abstract

The present study focuses on investigating the gamma-ray protection features of clay bricks for potential use in radiation shielding fields. The study examined the physical and structural features that affect the performance of these stones in shielding γ-rays. The density (ρ, g/cm3) of the clay bricks samples was measured utilizing the MH-300A density meter. Additionally, the mineral structure within the annealed pressed clay samples was identification the XRD spectrometry. Moreover, the morphology and elemental chemical composition for the annealed bricks were examined using a Thermo Scientific Prisma E, USA field emission Scanning Electron Microscope (SEM) in conjunction with Energy Dispersive X-ray Spectroscopy. Besides, the shielding features of the clay bricks were analyzed using the experimentally measurements (by NaI (Tl) scintillation detector), XCOM software, and Monte Carlo Simulation over the γ-ray energy interval of 0.033–1.332 MeV. The findings of the study indicate that an increase in the pressure rate within the clay bricks samples leads to the rise in their density (from 1.62 to 1.87 g/cm3). This increase in density is accompanied by a decline in both porosity (Φ, %) (from 34.75 to 26.21 %) and water absorption (K, %) (from 26.21 to 14.74 %) factors. Furthermore, the increase in pressure rate from 7.61 to 114.22 MPa also results in an increase in the linear attenuation coefficient (μ, cm−1) of the clay bricks under study. This is achieved by increasing the μ values from 0.39 to 0.43 cm−1, from 0.13 to 0.15 cm−1, and from 0.09 to 0.10 cm−1, at 0.081, 0.511 and 1.173 MeV, respectively. The synthetic bricks offer a lead-free and efficient option for protection, making them ideal for use in nuclear facility start-ups or in areas with radiation exposure.
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压力率对新型轻质粘土砖的物理、结构和伽马射线屏蔽能力的影响
本研究的重点是调查粘土砖的伽马射线防护特性,以确定其在辐射屏蔽领域的潜在用途。研究考察了影响这些石头屏蔽γ射线性能的物理和结构特征。使用 MH-300A 密度计测量了粘土砖样品的密度(ρ,克/立方厘米)。此外,还利用 XRD 光谱法鉴定了退火压制粘土样品中的矿物结构。此外,还利用美国 Thermo Scientific Prisma E 场发射扫描电子显微镜(SEM)和能量色散 X 射线光谱仪对退火砖的形态和元素化学成分进行了检测。此外,还利用实验测量(通过 NaI (Tl) 闪烁探测器)、XCOM 软件和蒙特卡罗模拟,在 0.033-1.332 MeV γ 射线能量区间内分析了粘土砖的屏蔽特性。研究结果表明,粘土砖样品内压力率的增加导致其密度上升(从 1.62 克/立方厘米增至 1.87 克/立方厘米)。在密度增加的同时,孔隙率(Φ,%)(从 34.75% 降至 26.21%)和吸水率(K,%)(从 26.21% 降至 14.74%)均有所下降。此外,压力率从 7.61 兆帕增加到 114.22 兆帕也导致了所研究粘土砖线性衰减系数(μ,cm-1)的增加。在 0.081、0.511 和 1.173 MeV 下,μ 值分别从 0.39 增加到 0.43 cm-1、从 0.13 增加到 0.15 cm-1 和从 0.09 增加到 0.10 cm-1。合成砖提供了一种无铅、高效的防护选择,非常适合用于核设施的启动或辐射暴露区域。
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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