Ahmad Nasuha, Idris Mohd Idzat, Hussin Azimah, Abdul Karim Julia, Azreen N M, Zainon Rafidah
School of Applied Physic, Faculty of Science and Technology, The National University of Malaysia, 43600, Bangi , Selangor, Malaysia.
Department of Earth Science and Environment, Faculty of Science and Technology, The National University of Malaysia, 43600, Bangi, Selangor, Malaysia.
Sci Rep. 2024 Oct 29;14(1):26029. doi: 10.1038/s41598-024-76402-0.
Concrete has been widely utilized as a radiation shielding material due to its properties and structural integrity. This study aims to evaluate the efficiency of ordinary concrete versus barite concrete as radiation shielding materials, focusing on the physical aspects and changes in crystal size lattice parameters after neutron irradiation. Specifically, the research investigates the shielding effectiveness of these materials across different grades (M15, M25, M35, and M45) against gamma-ray sources Cobalt-60 and Caesium-137. The methodology involves measuring the linear attenuation coefficient (μ), half value layer (HVL), tenth value layer (TVL), and mean free path (MFP). Additionally, X-ray diffraction (XRD) was employed to assess crystallite size and lattice parameter changes post-irradiation for neutron irradiation. Results indicate that incorporating barite as an aggregate significantly enhances the density and crystallite macroscopic properties of the concrete. Irradiation with Cobalt-60 and Cesium 137 revealed that ordinary concrete has a lower linear attenuation (μ) ranging from 0.172 to 0.195 cm, with consistent mass attenuation across all grades at 0.81 cm/g. XRD analysis demonstrated a rightward shift in the SiO₂ and BaSO₄ peaks post-irradiation, signifying crystalline expansion. In terms of lattice parameters, the d-value showed a notable decrease of 0.10 after 48 h of irradiation in grade 25, while the most significant increase of 0.02 occurred after 24 h of irradiation in grades 15 and 45. In conclusion, barite concrete proves to be more effective for radiation shielding in nuclear facilities, whereas ordinary concrete is suitable for medical shielding, or facilities exposed to lower radiation doses.
由于混凝土的特性和结构完整性,它已被广泛用作辐射屏蔽材料。本研究旨在评估普通混凝土与重晶石混凝土作为辐射屏蔽材料的效率,重点关注中子辐照后的物理特性以及晶体尺寸晶格参数的变化。具体而言,该研究调查了这些材料在不同等级(M15、M25、M35和M45)下对钴 - 60和铯 - 137伽马射线源的屏蔽效果。该方法包括测量线性衰减系数(μ)、半值层(HVL)、十分之一值层(TVL)和平均自由程(MFP)。此外,采用X射线衍射(XRD)来评估中子辐照后微晶尺寸和晶格参数的变化。结果表明,加入重晶石作为骨料可显著提高混凝土的密度和微晶宏观性能。用钴 - 60和铯 - 137辐照后发现,普通混凝土的线性衰减(μ)较低,范围为0.172至0.195厘米,所有等级的质量衰减均一致,为0.81厘米/克。XRD分析表明,辐照后SiO₂和BaSO₄峰向右移动,表明晶体膨胀。在晶格参数方面,25级在辐照48小时后d值显著下降0.10,而15级和45级在辐照24小时后d值增加最为显著,为0.02。总之,重晶石混凝土在核设施中对辐射屏蔽更有效,而普通混凝土适用于医疗屏蔽或暴露于较低辐射剂量的设施。