Fluka and microshield simulation assessment of nuclear radiation attenuation by binary nanocomposites

• Published in: Radiation physics and chemistry (Oxford, England : 1993) England : 1993), 2025-04, Vol.229, p.112409, Article 112409
• Main Authors: El-Taher, Atef, Zakaly, Hesham MH, Allam, Elhassan A., El- Sharkawy, Rehab M., Al Meshari, Meshari, Soliman, Abdallah M., Salih, Mohammed, Alahmad, Haitham, Mahmoud, Mohamed E.
• Format: Article
• Language: English
• Subjects: FLUKA; Gamma radiation shielding; Microshield; Nuclear attenuation
• ISSN: 0969-806X
• DOI: 10.1016/j.radphyschem.2024.112409

In this work, a theoretical simulation study using the FLUKA software was implemented to estimate the diverse values of radiation shielding parameters such as mass attenuation coefficient, μm, mean free path, MFP, atomic cross-section, σa, effective removal cross-sections for fast neutrons, ΣR, effective electron density, Neff, and effective atomic number, Zeff, for various composition concentrations of nano bentonite doped with N–HgO. The prepared nanocomposite materials were characterized by using XRD, and SEM to establish the morphological and structural properties. It was found that both the value of density and, μm, increase by increasing the concentration of N–HgO. The study focused on the prepared composite's computerized shielding behavior in the region of 81 to 2.614 × 103 keV. The mass attenuation coefficient was determined at different photon energies for example at 1173 keV for 0% N–HgO μm was 0.054 but cm2/g it was found to be 0.058 cm2/g for 40% N–HgO, and at 1332 keV was 0.055 cm2/g for 0% N–HgO, and 0.050 cm2/g for 40% N–HgO. On the other hand the attenuation toward neutrons was established and the effective removal cross-sections for fast neutrons ΣR values increased as the following; 0-Hg (0 wt %) (0.0932 cm−1) < 1-Hg (10 wt %) (0.0948 cm−1) < 2-Hg (20 wt %) (0.0983 cm−1) < 3-Hg (30 wt %) (0.0988 cm−1) < 4-Hg (40 wt %)(0.1019 cm−1). The fact that the 4-Hg (40 wt %) N–HgO within nano bentonite samples has the highest ΣR may be due to the large elemental composition of high-Z. It was concluded that the proposed composite may be used in nuclear safety applications as radiation exposure protection. •A theoretical simulation study has been investigated using the FLUKA software.•Estimation the following μm, MFP, σa, ΣR, Neff, and Zeff from this study.•The value of density and, μm, has been increased by increasing the concentration of N–HgO.•The NBentonite intercalated with NHgO is suitable for γ-nuclear radiation shielding.