Synthesis, physical, structure, mechanical and ionizing radiation shielding properties of some bismuth-based alloys: Comparative investigation

IF 2.8 3区 物理与天体物理 Q3 CHEMISTRY, PHYSICAL Radiation Physics and Chemistry Pub Date : 2025-04-01 Epub Date: 2025-01-03 DOI:10.1016/j.radphyschem.2025.112510
Abdelmoneim Saleh , Nermin Ali Abdelhakim
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引用次数: 0

Abstract

Due to the harmful effects of X-rays, gamma rays, neutrons, and heavy charged ions (such as protons and alpha particles) caused by radiation exposure, scientific investigation is still needed to find and develop materials that can act as radiation shields. Four Bi-based alloys (Bi–10Zn, Bi–10Sn, Bi–10In and Bi–10Ag) have been prepared utilizing melt-spinning technique. These alloys were composed of high purity elements such as Bi, Zn, Sn, In and Ag. Utilizing X-ray diffraction, the crystal structure of the prepared alloys was examined. The mechanical features in terms of Vickers hardness Hv and the creep behavior have been determined using Vickers microhardness test machine for the prepared alloys. The rapid solidification process had positive effects on the Vickers hardness Hv of the alloys due to several factors, including the refinement of grain size, enhanced alloy homogeneity, elimination of grain boundary segregation, increased solubility of solute elements, and the formation of new metastable crystalline structures, as well as a reduction in the degree of order. The WinXCom program was used to evaluate the shielding efficiency of various Bi-alloys against X/gamma radiation in the energy range of 0.015–15 MeV. Compared to other typical shielding materials and recently researched substances, the studied alloys demonstrate effective gamma shielding properties. The Sn–50Ag alloy exhibit superior mechanical and shielding against gamma rays performance. Consequently, the Bi–10Ag alloy strike a favorable balance between shielding and mechanical performance, making them suitable for radiation protection. Additionally, when compared to all other prepared alloys, conventional neutron shielding materials, and recently studied substances, the Bi–10Zn and Bi–10Ag alloys possesses the highest capability for absorbing neutrons. Lastly, the Bi–10Ag alloy demonstrates exceptional performance in attenuating protons (H+1) and alpha particles (He+2) in terms of projected range (PR) and stopping power (MSP). These findings indicate that the Bi–10Ag alloy offer excellent nuclear shielding and mechanical performance, making it well-suited for various applications, including nuclear waste storage, industrial processes, and medical applications.
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几种铋基合金的合成、物理、结构、力学和电离辐射屏蔽性能的比较研究
由于x射线、伽马射线、中子和重离子(如质子和α粒子)在辐射照射下造成的有害影响,仍然需要科学研究来寻找和开发可以作为辐射屏蔽的材料。利用熔融纺丝技术制备了4种铋基合金(Bi-10Zn、Bi-10Sn、Bi-10In和Bi-10Ag)。这些合金由Bi、Zn、Sn、In和Ag等高纯元素组成。利用x射线衍射对合金的晶体结构进行了表征。用维氏显微硬度试验机对制备的合金进行了以维氏硬度Hv为指标的力学性能和蠕变性能的测定。由于晶粒尺寸细化、合金均匀性增强、晶界偏析消除、溶质元素溶解度增加、新的亚稳晶结构形成以及有序度降低等因素,快速凝固过程对合金的维氏硬度Hv有积极影响。利用WinXCom程序对各种铋合金在0.015 ~ 15 MeV能量范围内对X/ γ辐射的屏蔽效能进行了评价。与其他典型屏蔽材料和近年来研究的材料相比,所研究的合金具有有效的屏蔽性能。Sn-50Ag合金具有优异的机械性能和屏蔽伽马射线的性能。因此,Bi-10Ag合金在屏蔽和机械性能之间取得了良好的平衡,使其适合辐射防护。此外,与所有其他制备的合金、传统的中子屏蔽材料和最近研究的物质相比,Bi-10Zn和Bi-10Ag合金具有最高的吸收中子的能力。最后,Bi-10Ag合金在衰减质子(H+1)和α粒子(He+2)方面表现出优异的投射范围(PR)和停止功率(MSP)。这些发现表明,Bi-10Ag合金具有优异的核屏蔽和机械性能,非常适合各种应用,包括核废料储存、工业过程和医疗应用。
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来源期刊
Radiation Physics and Chemistry
Radiation Physics and Chemistry 化学-核科学技术
CiteScore
5.60
自引率
17.20%
发文量
574
审稿时长
12 weeks
期刊介绍: Radiation Physics and Chemistry is a multidisciplinary journal that provides a medium for publication of substantial and original papers, reviews, and short communications which focus on research and developments involving ionizing radiation in radiation physics, radiation chemistry and radiation processing. The journal aims to publish papers with significance to an international audience, containing substantial novelty and scientific impact. The Editors reserve the rights to reject, with or without external review, papers that do not meet these criteria. This could include papers that are very similar to previous publications, only with changed target substrates, employed materials, analyzed sites and experimental methods, report results without presenting new insights and/or hypothesis testing, or do not focus on the radiation effects.
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