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Based on the experimental and theoretical radiation attenuation, this study produced and tested a composite material made of polyester reinforced with SnO at varied concentrations and abbreviated as Pol-SnOx, where x = 0–60% with steps of 20 wt% Also, the polyester samples were doped with SnO of different particle sizes: Micro, Nano, and 50% Micro/50% Nano mix to investigate the effect of the particle size on the radiation attenuation performance. In the photon energy range of 0.015–15 MeV, their radiation shielding properties were empirically determined using an HPGe detector and theoretically determined using Phy-X/PSD software. The linear attenuation coefficient (LAC) values dropped from 1.361 to 0.022 cm−1 for Pol-SnO0, from 13.611 to 0.033 cm−1 for Pol-SnO20, from 31.700 to 0.049 cm−1 for Pol-SnO40, and from 61.076 to 0.076 cm−1 for Pol-SnO60 in the photon energy (Eγ) range from 0.015 to 15 MeV. The LAC values of the fabricated Pol-SnOx samples increased as the SnO concentrations increased. Also, the addition of 50% Micro/50% Nano mix particle size of the SnO to the polyester significantly increased the values of the LAC. The percentages of LAC improvement of SnO nano-particles were 16.625%, 13.236%, 8.714%, and 7.935% at the Eγ values of 0.059, 0.661, 1.173, and 1.332 MeV, respectively. Also, the LAC values were enhanced by adding SnO containing 50% Micro/50% Nano mix particles by 19.097%, 15.271%, 9.854%, and 9.071% at the Eγ values of 0.059, 0.661, 1.173, and 1.332 MeV, respectively, when compared to microparticles. The addition of 50% Micro/50% Nano Mix of SnO with 60% content to the polyester showed the highest LAC and radiation protection efficiency and lowest half-value layer and transmission factor among the other samples due to increased SnO doping and interparticle distances of the Micro and Nano mix.

Radiation and nuclear technologies have side effects in addition to their important applications, so appropriate shields must be used to protect users and the public from high doses as a result of exposure to this radiation. In this work, the attenuation coefficients for polyester composites doped with waste iron filings (IFs) were studied. Six samples of different IF concentrations were manufactured, namely, Poly, Poly-IF20, Poly-IF30, Poly-IF40, Poly-IF50, and Poly-IF60 (where Poly-IF60 represents 40% polyester and 60% IF). We measured the attenuation factors using high purity germanium (HPGe)-detector along with three radioactive sources 241Am (emitting energy of 0.06 MeV), 137Cs (emitting energy of 0.662 MeV), and Co-60 (emitting energy of 1.173 and 1.333 MeV). We compared the linear attenuation coefficient (LAC) obtained by theoretical (i.e., XCOM software) and experimental (i.e., HPGe-detector) approaches for the prepared polyester composites at various photon energies (0.060, 0.662, 1.173, and 1.333 MeV). The greatest difference between the LAC values of the samples occurs at 0.060 MeV, where the Poly-IF60 sample has a much greater LAC than the other shields, followed by the Poly-IF50 sample, Poly-IF40 sample, and so on until the pure polyester shield. Specifically, their values are equal to 0.245, 0.622, 0.873, 1.187, 1.591, and 2.129 cm−1 for Poly, Poly-IF20, Poly-IF30, Poly-IF40, Poly-IF50, and Poly-IF60, respectively. We calculated the transmission factor (TF) and the radiation shielding efficiency (RSE), and found that the TF for Poly-IF30 is equal to 28.82%, 77.94%, 82.75%, and 83.75% at 0.060, 0.662, 1.173, and 1.333, respectively, while its RSE is equal to 82.57%, 24.00%, 18.80%, and 17.72%, respectively. The fast neutron removal cross-section (FNRC) of the polyester samples was calculated and the values increase when more Ifs are added to the samples. More specifically, the FNRC values are equal to 0.095, 0.100, 0.103, 0.107, 0.110, and 0.113 cm−1 for Poly, Poly-IF20, Poly-IF30, Poly-IF40, Poly-IF50, and Poly-IF60, respectively.