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The substitution of La2O3 by Tb2O3 was studied for glass samples with a chemical composition described by: 75P2O5 + (25 − x) La2O3 + xTb2O3, where x = 5, 10, 15, 20 mol%. The mechanical properties were predicted via the Makishima–Mackenzie model. The study demonstrated that when increasing the Tb2O3 content from 5 to 20 mol%, the elastic moduli of the glasses decreased, while the dissociation energy, packing density, and micro-hardness increased. In addition, the radiation shielding properties were studied using the MCNP5 code, which was utilized to simulate the linear attenuation coefficient (LAC) of the investigated samples. Furthermore, the mass attenuation coefficients (MAC) of the glasses were determined. The highest MAC was reported for the sample with 20 mol% of Tb2O3 and decreased from 0.358 to 0.0515 cm2/g between 0.184 and 1.408 MeV. Furthermore, the effective atomic number (Zeff), equivalent atomic number (Zeq), exposure buildup factor (EBF), and the energy absorption buildup factor (EABF) of the glasses were calculated utilizing BXCOM software. The substitution of La2O3 by Tb2O3 was revealed to enhance the shielding features of the TLP samples.

Geant4 simulation was applied to correct the coincidence summing (CS) effect in detecting a volumetric γ-ray sources, and this technique was applied to a152Eu standard sources. The radioactive sources were a liquid cylindrical, rectangular, and Marinelli beaker shapes of different volume for each one. Radionuclide track (RT) including coincidence summing and monoenergetic track without coincidence summing. The results obtained from two approaches compared with the experimental data and the modified KORSUM code for cylindrical γ-ray source. The comparison showed that the adopted method in this investigation is useful for coincidence summing corrections for a voluminous γ-ray sources.Moreover, this technique requires far less computation time than the techniques that depend on the calculation of total efficiency.

In the present work, untreated Iraqi sand with grain sizes varied between 100 and 200 μm was used to produce a colored glass sample that has shielding features against the low gamma-ray energy. Therefore, a weight of 70–60 wt % sand was mixed with 9–14 wt% B2O3, 8–10 wt% Na2O, 4–6 wt% of CaO, 3–6 wt% Al2O3, in addition to 0.3% of Co2O3. After melting and annealing the glass sample, the X-ray diffraction spectrometry was applied to affirm the amorphous phase of the fabricated glass samples. Moreover, the X-ray dispersive energy spectrometry was used to measure the chemical composition, and the MH-300A densimeter was applied to measure the fabricated sample's density. The Makishima-Makinzie model was applied to predict the mechanical properties of the fabricated glass. Besides, the Monte Carlo simulation was used to estimate the fabricated glass sample's radiation shielding capacity in the low-energy region between 22.1 and 160.6 keV. Therefore, the simulated linear attenuation coefficient changed between 10.725 and 0.484 cm−1, raising the gamma-ray energy between 22.1 and 160.6 keV. Also, other shielding parameters such as a half-value layer, pure lead equivalent thickness, and buildup factors were calculated. © 2022 Korean Nuclear Society Princess Nourah Bint Abdulrahman University, PNU: PNURSP2022R28 The authors express their gratitude to Princess Nourah bint Abdulrahman University Researchers Supporting Project number (PNURSP2022R28), Princess Nourah bint Abdulrahman University, Riyadh, Saudi Arabia.

The effect of substitution Pb2O3 by CuO content was studied for 75% Li2B4O7 + (25 − x)Pb2O3 + xCuO glass system where x = 0, 5, 10, 15, 20, and 25 wt%. The mechanical and radiation shielding properties were evaluated for the investigated glass samples. The mechanical properties included Young's, shear, bulk, longitudinal, Poisson ratio, and micro-hardness were computed theoretically based on the packing factor (Vi) and dissociation energy (Gi) of the metal oxides constituting the existing glass samples using the Makishima–Mackenzie model. The obtained results depicted the insertion of CuO enhances the different mechanical parameters up to 20 mol% of the investigated LBPCu glasses. Furthermore, the radiation shielding properties were studied for the investigated LBPCu glass using the Monte Carlo N-particle transport code (MCNP-5) simulation. MCNP-5 was used to detect the simulated linear attenuation coefficient (LAC) and then mass attenuation coefficient (MAC) and other factors based on various gamma-ray sources with energies of 0.24, 0.66, 1.17, 1.33, and 1.40 MeV. The results showed that LAC's highest value decreased from 0.578 to 0.320 cm−1 for glasses LBPCu0 and LBPCu25, respectively, at low energy of 0.284 MeV. Moreover, the effective and equivalent atomic numbers (Zeff and Zeq), buildup factor (EBF), and absorption buildup factor (EABF) were evaluated for the investigated LBPCu glass using the BXCOM program. The results revealed that the shielding properties of the investigated glasses improved by the insertion of CuO content.

The aim of this work is to study the radiation shielding properties of cement samples with waste glass incortated into its composition. The mass attenuation coefficient (MAC) of the samples were experimentally determined to evaluate their radiation shielding ability. The experimental coefficient was evaluated using NaI detector for gamma energies between 59.53 keV and 1408.01 keV using different radioactive point sources Am-241, Eu-152, Co-60, and Cs-137, and the gamma transmission parameters half-value layer, mean free path, and transmission factor were calculated. The theoretical coefficient of the composites was determined using Geant4 and XCOM software. The results were also compared against Geant4 and XCOM simulations by calculating the relative deviation between the values to determine the accuracy of the results. In addition the mechanical properties (including Compressive and porosity) as well as the thermogravimetric analysis were tested for the present samples. Overall, it was concluded that the cement sample with 50% waste glass has the greatest shielding potential for radiation shielding applications and is a useful way to reuse waste glass.

The effect of the incorporation of the SrO to the Li2O -K2O-B2O3 glasses prepared through melt quenching technique has been studied. The density of the samples increases from 2.2057 to 2.8050 g/cm3. The XRD spectra reveals that the prepared samples are amorphous in nature. The five major bands having various IR peaks around 480 cm−1, 525 cm−1, 700 cm−1, 892 cm−1, 910 cm−1, 1225 cm−1, 1360 cm−1, and 1740 cm−1 are observed in the FTIR spectra. The gamma ray shielding properties have been calculated at several gamma-ray energies between 0.015 and 15 MeV using Phy-X software. LiKBSr20 with highest linear attenuation coefficient and effective atomic number is the best attenuator out of the fabricated LiKBSr-X glasses. The radiation protection efficiency (RPE) improves on addition of SrO and the RPE values indicate that these glasses can be developed as shielding glasses for the low-energy photons.

In this work, series of novel metatitanate ceramics mixed with SnO2 (BTO, STO, BTO@SnO2, STO@SnO2) have been successfully prepared via the solid-state reaction route. The XRD patterns indicate that the BTO, BTO@SnO2 crystallized into the tetragonal structure, where a cubic structure was obtained for STO and STO@SnO2 ceramics. The refinement of the data revealed a variation in lattice parameters of the ceramics. The optical properties were analyzed by using an ultra–visible spectrophotometer. The results showed that values of optical band gap Eg are in the range of 3.0–3.3 eV for all ceramics. Moreover, the radiation shielding factors were reported and the results demonstrated that there is a decreasing tendency in the linear attenuation coefficient (LAC) as the energy changes from 0.2234 to 2.506 MeV. From the LAC results, the BaTiO3 ceramic is the most influential at blocking radiation. The half-value layer (HVL) was examined and we found a notable difference between the HVL of the four prepared ceramics. BTO has the least HVL and takes the range 0.725–4.53 cm between 0.2234 and 2.506 MeV. HVL minimum value is obtained at 0.2234 MeV for all compositions and equals 0.725, 0.895, 1.559, and 1.265 cm for BaTiO3, BTO@SnO2, STO, and STO@SnO2 respectively. The change in the transmission factor (TF) of the fabricated ceramics against the energy and the thickness is discussed, and we found that the four ceramics have the minimum TF at 0.2234 MeV and the greatest at 2.506 MeV. The TF for BTO is 56.31% at 0.2234 MeV, 73.76% at 0.356 MeV, 80.25% at 0.511 MeV and 91.3% at 2.506 MeV. The TF results suggest that the fabricated ceramics are good attenuators at low energies. The radiation shielding results confirmed that the prepared ceramics can be exploited as good candidates for radiation shielding applications.

The purpose of this study is to examine the clinical radiation effects on patients with various stents. Several previous researches focused on the mechanical and physical features of the stents, but there have been few studies that focus on the interaction with radiological and clinical radiation. For stent material analysis, the ANSYS package program was employed. These materials and models are often built in three dimensions for three different types of stents made of three various materials. Estimates of blood pressure and thermal radiation were explored, as were the effects of non-ionizing radiation. Furthermore, the radiation attenuation characteristics of stent samples are investigated. The mass attenuation coefficient values are computed using MATLAB code over a large energy range of 0.015-15 MeV, and the findings are validated using theoretical WinXCom results. To determine the gamma-ray attenuation performances of the studied stent samples, variables such as the mass attenuation coefficient (MAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Z

We investigate the radiation shielding properties for four Te-based alloys. X-ray diffraction patterns revealed pure phases in all studied samples; however, a secondary phase is detected in the CrTe sample in good agreement with the literature. All samples’ densities were measured using the Archimedes principle. The mass attenuation coefficient (MAC) was calculated using Geant4 MC Toolkit and then compared with the XCOM data. Many photon-shielding properties were computed for all investigated samples based on the MAC. The Phy-X and SRIM were used to determine the fast neutron removal cross-section (ΣR) and projected range, respectively. As a result, PbTe shows superior shielding features compared to the rest of the investigated samples to use this sample in different shielding applications.

Zirconium–Titanium–Thallium Ternary Oxide Ceramic (0.5ZrO2-(0.5-x)TiO2-xTl2O3 (x = 0, 0.05, 0.15, 0.2 and 0.25 mol %) was synthesized via solid-state reaction. Advanced analytical technique like Scanning electron microscopy (SEM), Fourier transform infrared (FTIR), and X-Ray diffraction (XRD) were used to study the microstructure and the solubility of thallium oxide in the ZrO2/TiO2 mixture. The diffuse reflectance and photoluminescence techniques were employed to investigate the optical properties of the prepared alloys for various Tl2O3 mol% concentrations. In addition, the mass attenuation coefficient (MAC) for the synthesized ceramic samples was measured experimentally and compared with XCOM data. Our experimental values were in good agreement with XCOM data. Various shielding parameters for gamma-rays, neutron, proton, and alpha particles were evaluated using XCOM, Phy-X, and SRIM programs. The Tl2O3 content linearly affects the gamma-rays shielding parameters, while the Tl2O3 content has an inverse relationship with neutron and charged particle shielding parameters. This study proved that our Zirconium–Titanium–Thallium Ternary Oxide Ceramic samples can be applied as ionizing radiation shielding material very well.

Recently, the use of ionizing radiation in various fields leads to an increased demand for shielding materials. This work aims to study the structural and radiation shielding properties of two groups of perovskite ceramics. Fourier transform infrared and X-ray diffraction were utilized to investigate current samples’ structure, and various radiation shielding parameters were determined to explore the current samples’ ability to absorb radiation within an energy range from 0.284 to 2.506 MeV using the Phy-X program. The Fourier transform infrared results revealed one vibration band for BaTiO3–ZrO2 located at 507 cm−1, two bands centered at 835 and 520 cm−1 for the BaTiO3-Mo sample, and five bands located at 435, 520, 539, 615, and 775 cm−1 for SrMnO3–ZnO and SrMnO3–TeO2. Simultaneously, the X-ray diffraction displays the hexagonal phase for SrMnO3 and the tetragonal phase for BaTiO3 samples. The BaTiO3-Mo sample has the highest density, packing density, and Poisson’s ratio compares with other samples. According to gamma shielding results, the SrMnO3–ZnO and BaTiO3–ZrO2 samples appear the lowest and highest absorption ability, respectively. On another side, the SrMnO3–TeO2 sample has the highest removal cross-section for fast neutrons. From obtained results, it can be concluded that the BaTiO3–ZrO2 sample has an excellent capacity to stop gamma-ray, while SrMnO3–TeO2 can be used to prevent neutrons.

The aim of this study is to examine the effect of Bi2O3 concentration and particle size on Bi2O3 glass. The tested glasses had the composition of SiO2–Bi2O3–CaO–MgO–B2O3–K2O–Na2O–ZnO. Ordinary glass was compared with glasses with 10% Bulk Bi2O3, 10% Bi2O3 Nanoparticles (NPs), 20% Bulk Bi2O3, and 20% Bi2O3 nanoparticles. The mass attenuation coefficients (MACs) of all the investigated glasses were determined between 0.0595 MeV and 1.41 MeV. The results demonstrated that increasing the Bi2O3 content in the glass matrix improved their shielding capability, as well as showing that the NPs provided greater attenuation than the bulk Bi2O3 at the same concentration. The percent increase in the MAC between the bulk and nano Bi2O3 was also calculated and analyzed. From the MAC values, the LAC of the glass was determined and similar results were found compared to the MAC figure. The HVL and MFP of the glass were then analyzed and the results demonstrated that the glass with Bi2O3 NPs attenuated the same amount of photons at a smaller thickness, making the NP shield more effective. The heaviness of the samples illustrated that all the tested samples have a smaller weight than pure lead, making them more desirable. The attenuation factor of the glass (Att. Factor %) showed that increasing the Bi2O3 content in the samples and increasing the thickness of the shields both improve the shielding capability of the glass. Lastly, the dlead of the glasses was determined, indicating that the greatest reduction in thickness occurs near the K-absorption edge of bismuth. Overall, the glass with 20% Bi2O3 NPs demonstrated to have the greatest potential for radiation shielding applications.

Evaluation of the mechanical and shielding features is performed for glasses with the composition xBi2O3-(80-x) TeO2-10GeO2-10B2O3 with different concentrations x = 40, 50, 60, and 65 mol%. The mechanical parameters are summarized utilizing the Makishima-Mackenzie model. The elastic moduli such as Young, bulk, shear, and longitudinal are computed. The obtained results depict the elastic moduli affected by the replacement TeO2 with Bi2O3 content. The maximum values of elastic moduli are 61.822, 40.706, 24.790, and 73.761 for Young, bulk, shear, and longitudinal, respectively, of the inspected glasses utilizing the Monte Carlo simulation code (MCNP-5). The mass attenuation coefficient (μρ) and the half-value thickness (HVT) were also calculated. The shielding ability is tested by comparing the mean free path of the studied glasses with the commercial glasses. Likewise, the accumulation of photons inside the glass’s material is determined using the BXCOM program. Finally, it can deduce the discussed fabricated glasses are suitable to apply in diverse applications of radiation protection.