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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.

In an attempt to reutilize marble waste, a new approach is presented in the current study to promote its use in the field of shielding against ionizing radiation. In this study, we aimed to develop a novel and sustainable/eco-friendly lead-free radiation shielding material by improving artificial marble (AM) produced from marble waste combined with polyester by reinforcing it with bismuth oxide (Bi2O3) nanoparticles. Six samples of AM samples doped with different concentrations ( 0 % ,   5 % ,   10 % ,   15 % , 20 % , and 25 % ) of Bi2O3 nanoparticles were prepared. The linear attenuation coefficient ( L A C ) values were measured experimentally through the narrow beam method at different energies (0.0595   M e V , 0.6617   M e V , 1.1730   M e V , and 1.330   M e V ) for all samples with various concentrations of Bi2O3. Radiological shielding parameters such as half value layer ( H V L ), tenth-value layer ( T V L ), and radiation shielding efficiency ( R S E ) were estimated and compared for all the different samples. The results prove that increasing the concentration of Bi2O3 leads to the enhancement of the radiation shielding properties of the AM as a shielding material. It was observed that as the energy increases, the efficiency of the samples falls. High energy dependence was found when calculating the H V L and T V L values of the samples, which increased with increases in the energy of the incident photons. A comparison between the sample with the most efficient gamma radiation attenuation capability (AM- 25 % ), concrete, and lead was conducted, and a discussion regarding their radiation shielding properties is presented herein. The results show that the AM- 25 % sample is superior to the ordinary concrete over all the studied energy ranges, as evidenced by its significantly lower H V L s . On the contrary, lead is superior to the AM- 25 % sample over all the studied energy ranges owing to its unbeatable density as a shielding material. Overall, this new type of artificial marble has the potential to be used as a radiation shielding material at low- to medium-gamma energy regions, specifically in medical imaging and radiation therapy. [ABSTRACT FROM AUTHOR]

Five glass samples with the following chemical formation: 21.5 SiO2-58.5B2O3-(20-x) ZnO- xLa2O3, where x = 0–10 mol% were fabricated utilizing melt quenching. With an increase in La2O3, the glasses' density increased from 3.174 to 4.754 g/cm3. Experimental data were used to evaluate the mechanical characteristics, and the Makishima and Mackenzie model's semi-empirical methods were used to analyze the elastic properties. As the amount of La2O3 increases, there's a noticeable rise in the velocity of ultrasonic waves. This heightened velocity is likely linked to the strengthening or increased rigidity of the glass network. Elastic moduli values of the glasses under investigation increase with an increase La2O3 content. Employing Phy-X/PSD code, the radiation attenuation behaviour of zinc borosilicate glasses with varying La2O3 concentrations were examined. With increased energy, the enhancement LAC decreases from 2.576 to 0.0375. The ZBSL10 glasses demonstrated strong mechanical and physical characteristics as well as radiation shielding capabilities. The features of the ZBSL glasses are particularly attractive for a variety of mechanical and shielding applications. [ABSTRACT FROM AUTHOR]

The composition of the pentagonal glass system, which is composed of 57B2O3-16SiO2-11BeO- (16-x) MgO-xLa2O3, x = (0 ≤ x ≤ 16 mol %), has been synthesized by the melt quench process. XRD diffractograms' wide haloes testified to the materials' amorphous state. It was discovered that, density increased in response to La2O3 concentration, whereas molar volume decreased. Additionally, the ranges of longitudinal and shear velocities are 4730 to 5085 m/s and 2685–2895 m/s, respectively. The elastic moduli for longitudinal range between 71.9–154.3 GPa, shear range between 23.2–50 GPa, bulk range between 23.2–50 GPa, and Young's range between 58.5–126 GPa, respectively. The study employed Phy-X/PSD code to examine the radiation attenuation behaviour of magnesium beryllia-borosilicate, also known as (BMBSLa) glasses, at varying concentrations of La2O3. We examined the relationship among the half value layer (HVL) and density. HVL values at a density of 3.213 g/cm3 range from 0.0087 to 11.746 cm and at density of 5.967 g/cm3 range from 0.02 to 5.727 cm at (0.015–15 MeV). Tenth value layer (TVL) and mean free path (MFP) are evaluation and comparison between HVL, TVL and MFP for the same glass at specific energy were also conducted. The glass samples under investigation are excellent candidates for usage in the field of shielding radiation because they are more transparent. [ABSTRACT FROM AUTHOR]