Abstract
In the present work, the nuclear radiation shielding proficiency of eight glassy alloys (Gd25RE25Co25Al25 (RE = Tb, Dy and Ho)) containing different amounts of rare earth elements was investigated with MCNPX simulation codes. Mass attenuation coefficients (μ/ρ) of the glassy alloys were simulated in the energy interval of 0.2–20 MeV by exploiting MCNPX codes, and the generated data were found to match with theoretical WinXCOM results. Next, other crucial photon attenuation parameters, effective atomic number (Zeff), Half Value Layer (HVL), and Mean Free Path (MFP), were gotten out using μ/ρ values. It was seen that Er20Tm20 and Er20Tb20 samples replaced with Er by Gd had the highest Zeff and μ/ρ values, whereas HVL and MFP values were the smallest among the other glassy alloys. Geometric progression (GP) procedure was enjoyed to achieve the exposure and energy absorption buildup factors (EBF and EABF) for the glassy alloys proposed. EABFs and EBFs took the largest and lowest values for Gd25Tb25 and Er20Tm20, respectively, to the other samples. Furthermore, the glassy alloys’ neutron reduction abilities were estimated by acquiring fast neutron removal cross-sections (∑R). It was noticed that the ∑R values of the glassy alloys are increased with the rising sample density and seen to be comparable to ∑R values of water and ordinary concrete. The results obtained from this study are important in that they show that glassy alloys can be used as radiation shielding.
Highlights
In the last few years, ionizing radiation has more attractive applications in different fields such as medical area, industry branch, and agricultural field
For verifying the data generated with MCNPX codes, μ/ρ values of eight glassy alloys were derived using WinXCOM software
The results found for μ/ρ are given with relative deviations between both methods
Summary
In the last few years, ionizing radiation has more attractive applications in different fields such as medical area (radiotherapy, radiology, nuclear medicines), industry branch (test the void and insertion into the inner part of the material), and agricultural field (to differentiate between different types of woods, save the plants seeds and foods). These radiations, especially γ-photons, can be travelled for a long kilometre and have high power to penetrate materials. Several researchers and investigators have devoted significant efforts to finding more suitable radiation protection materials [2,3,4,5,6,7,8]. In this literature, Kilic et al 2021 [9] studied the impact of Eu2O3 additive to zinc-borate on physical and nuclear radiation shielding properties of different types of samples, obtained in density and molar volume variations. The experimental analyses and simulation by MCNPX (version 2.6.0) showed that maximum nuclear shielding competence had been provided with maximum Eu2O3
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