The Sn-Bix (x = 30, 40, 50, 60 and 70%) radiation shielding alloys were prepared using a melting process of the alloying material in a ceramic crucible at 200 °C for 120 min. The structural characterization for synthesized samples was carried out using X-ray Diffraction technique (XRD). The hardness and elastic properties of the prepared alloys was measured using micro-indentation creep technology and tensile test machine respectively. XRD pattern indicated that that the crystal size of Sn phase is lowered by increasing Bi concentration in the Sn matrix. The hardness decreases as the dwell time increases. The hardness values and elastic properties (in terms of young modulus) were significantly improved due to the decrease in the crystallite size by increasing Bi content. The stress exponent (n) value increase by increasing Bi content which mean that the mechanical properties improved due to increment of resistance. Furthermore, the produced alloys' nuclear shielding ability was investigated. The μm values were calculated using MCNP simulation code and XCOM software over a broad energy range of 0.015 MeV–15 MeV with good agreement between them. Several characteristics are estimated in order to properly understand the researched alloy's radiation and properties of neutron shielding. The findings showed that a higher Bi concentration causes the crystal size to decrease, improving the radiation shielding and mechanical qualities. The alloy Sn-70% Bi has a maximum increase of vicker hardness, tensile strength, and young's modulus. The findings of the shielding parameters indicate that the alloys under study are efficient gamma shielding materials in contrast to other typical shielding materials and materials that have been examined recently. The highest mechanical efficiency and rather strong gamma-ray shielding capabilities are found in the Sn–70Bi alloy. Owing to its ability to effectively balance mechanical performance and shielding, the Sn–70Bi are approved for use in radiation protection. In addition, when compared to all other manufactured alloys, typical neutron shielding materials, and recently investigated materials, the results further demonstrate that the Sn–70Bi alloy has the best neutron attenuation capability. Furthermore, in terms of mass stopping power (MSP) and projected range (PR), the Sn–70Bi alloy demonstrates the most effective attenuation for alpha particles (He+2) and protons (H+1). These results imply that the Sn–70Bi alloy provide superior mechanical performance and nuclear shielding for a range of applications including industrial, medicinal, and nuclear waste storage in the future.

中文翻译：

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电离辐射屏蔽效率和各种锡基合金的机械性能之间的良好平衡：比较分析


采用合金材料在 200 °C 陶瓷坩埚中熔化 120 分钟制备了 Sn-Bix （x = 30、40、50、60 和 70%） 辐射屏蔽合金。合成样品的结构表征是使用 X 射线衍射技术 （XRD） 进行的。分别采用微压痕蠕变技术和拉伸试验机测量了所制备合金的硬度和弹性性能。XRD 图谱表明，Sn 基体中 Bi 浓度的增加会减小 Sn 相的晶体尺寸。硬度随着停留时间的增加而降低。由于增加 Bi 含量降低了晶粒尺寸，硬度值和弹性性能（就年轻模量而言）得到了显着改善。应力指数 （n） 值随着 Bi 含量的增加而增加，这意味着由于电阻的增加，机械性能得到改善。此外，还研究了所制备合金的核屏蔽能力。μm 值是使用 MCNP 仿真代码和 XCOM 软件在 0.015 MeV–15 MeV 的宽能量范围内计算的，它们之间具有良好的一致性。为了正确理解所研究合金的辐射和中子屏蔽特性，估计了几个特性。研究结果表明，较高的 Bi 浓度会导致晶体尺寸减小，从而改善辐射屏蔽和机械质量。合金 Sn-70% Bi 的维克硬度、抗拉强度和杨氏模量增加最大。屏蔽参数的结果表明，与其他典型的屏蔽材料和最近检查的材料相比，所研究的合金是高效的 γ 屏蔽材料。 Sn-70Bi 合金具有最高的机械效率和相当强的伽马射线屏蔽能力。由于其能够有效平衡机械性能和屏蔽性能，Sn-70Bi 被批准用于辐射防护。此外，与所有其他制造的合金、典型的中子屏蔽材料和最近研究的材料相比，结果进一步证明 Sn-70Bi 合金具有最佳的中子衰减能力。此外，在质量阻止能力 （MSP） 和投影距离 （PR） 方面，Sn-70Bi 合金对 α 粒子 （He+2） 和质子 （H+1） 表现出最有效的衰减。这些结果表明，Sn-70Bi 合金为未来的一系列应用（包括工业、医药和核废料储存）提供了卓越的机械性能和核屏蔽。