Simulation study reveals enhanced gamma-ray and fast neutron shielding in samarium oxide-reinforced aluminosilicate ceramics, highlighting their viability for nuclear and medical radiation protection.
In this study, the radiation shielding performance of Sm2O3-reinforced aluminosilicate ceramics was systematically investigated over a wide photon energy range through a combined theoretical and Monte Carlo simulation approach. Photon attenuation characteristics were evaluated by calculating the mass attenuation coefficient (MAC) and linear attenuation coefficient (LAC) using EpiXS calculations and PHITS Monte Carlo simulations. In addition, key shielding parameters including the half-value layer (HVL), mean free path (MFP), effective atomic number (Zeff), and electron density (Nel) were determined to assess the practical radiation attenuation capability of the investigated compositions. The incorporation of Sm2O3 significantly enhanced photon attenuation performance owing to the high atomic number and density contribution of samarium within the ceramic matrix. Energy absorption buildup factor (EABF) and Exposure buildup factor (EBF) were evaluated as functions of photon energy and penetration depth. The buildup factors remained near unity at low energies and peaked in the intermediate energy region due to dominant Compton scattering. In addition to photon shielding behavior, the fast neutron removal cross sections (ΣR) of the investigated ceramics were theoretically evaluated. The results demonstrated a monotonic increase in ΣR with increasing Sm2O3 concentration, indicating an enhancement in fast neutron attenuation capability. Overall, the combined evaluation of photon attenuation parameters, buildup factors, and neutron removal cross sections confirms that Sm2O3 incorporation significantly improves the radiation shielding performance of aluminosilicate ceramics across a broad energy spectrum. These findings highlight the potential of Sm2O3 reinforced ceramic systems as advanced multifunctional shielding materials for medical radiation facilities, nuclear technologies, and industrial radiation protection applications.
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Halime Erzen Yıldız (2026) studied this question.
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