FeSO4、CuSO4、NiSO4 和 ZnSO4 化合物的辐射屏蔽参数化:使用 (XRF) 技术和蒙特卡罗 FLUKA 方法

Muataz Majeed
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引用次数: 0

摘要

不同硫酸盐化合物的质量衰减系数 (MAC) 可通过能量色散 X 射线荧光 (EDXRF)(又称 X 射线荧光 (XRF) 技术)进行估算。发射的 X 射线光子具有不同的能量,这取决于入射光子能量、原子量和被测材料的分子结构。使用 241Am(40 µci)获得的伽马射线源激发能量为 59.53 keV。不同元素(铁、镍、铜、锌)的硫酸盐化合物的 (MAC) 是通过测量纯元素及其化合物中 kα 的强度差来计算的。测定结果表明,FeSO4 中的 (µm) 值最大。这些结果与 XCOM 软件获得的理论值一致,此外,还利用 FLUKA Monte Carlo 仿真软件研究了光子与引入化合物相互作用的宽能量响应。使用 FLAIR 代码对这些化合物在 0.015-15 MeV 能量范围内的质量衰减系数(MAC)进行了数值评估。计算得出的 (µm) 用于生成重要的辐射防护因子,如线性衰减系数 (LAC)、半层值 (HVL)、有效原子序数 (Zeff) 和等效原子序数 (Zeq)。为了研究快中子和热中子辐射的屏蔽效果和效率,给出了去除截面ƩR。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Radiation shielding parameterizations of FeSO4, CuSO4, NiSO4 and ZnSO4 Compounds: using (XRF) technique & Monte Carlo FLUKA approach
The mass attenuation coefficient (MAC) for different sulphate compounds can be estimated by using the Energy Dispersive X-ray Fluorescence (EDXRF), also known as X-ray Fluorescence (XRF) technique. The X-ray photons emitted have different energies depending on incident photon energy, atomic weight, and molecular structure of tested material. The excitation energy of the gamma rays source with 59.53 keV was obtained by using 241Am (40 µci). The (MAC) for sulphate compounds of a different element (Fe, Ni, Cu, Zn) have been calculated by measuring the intensity difference for kα in pure elements and their compounds. The determined results showed that the maximum value for (µm) was in FeSO4. These results are consistent with the theoretical value obtained by the XCOM software in addition to investigating the wide energy response of photon interaction with the introduced compounds using the FLUKA Monte Carlo simulation software. The mass attenuation coefficient (MAC) of these compounds is numerically evaluated in the energy range 0.015-15 MeV using the FLAIR code. The computed (µm) is used to generate significant radiation protection factors such as the linear attenuation coefficient (LAC), half-layer value (HVL), effective (Zeff), and equivalent (Zeq) atomic number. For studying the shielding effectiveness and efficiency, for fast and thermal neutron radiation, the removal cross-section ƩR was given.
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