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This research intends to utilize melt-quenching technique in order to examine the radiation shielding capability of 10 % Mo, 10 % Na2O, 20 % PbO, and 60 % B2O3 glass system, with varying CaO, TiO2, CuO, Fe2O3 or Mo. XCOM and MCNP simulations were utilized to analyze the radiation shielding properties of the fabricated glasses. The results revealed CuO having the superior MAC of 49.91 cm2/g, then Fe2O3 with 49.24 cm2/g, followed by CaO with 49.10 cm2/g, and TiO2 with 48.49 cm2/g as the least. CuO and Fe2O3 were confirmed to have least HVL compared to CaO and TiO2. The value of the lead equivalent thickness showed fluctuation against the gamma energy, where it raisess within the photoelectric region and falls after the photoelectric region. The data reveal that, the lead equivalent thickness at 0.1 MeV were 7.88 cm, 7.86 cm, 7.81 cm and 7.80 cm for TiO2, Fe2O3, CaO, and CuO in the same order, respectively. The transmission factor (TF) raises as the gamma energy raises, having TiO2 as the highest with 76.068 %, while the radiation protection efficiency dropped as the energy raises.

The linear attenuation coefficients (LAC) of four soils (Black cotton (S1), Sandy (S2), Clay (S3), and Sandy (S4)) samples were measured at photon energies released from radioisotopes Co57 (122 keV), Ba133 (356 keV), 22Na (511 and 1275 keV), Cs137 (662 keV), Mn54 (840 keV), and Co60 (1330 keV) using a gamma spectrometer includes a NaI (Tl) scintillation detector. The experimental measurements were confirmed utilizing the Monte Carlo N-particle transport code. The linear attenuation coefficient values enhanced from 0.256 cm−1 to 0.296 cm−1 (at Eγ of 122 keV), from 0.126 cm−1 to 0.142 cm−1 (at Eγ of 662 keV), and from 0.0938 cm−1 to 0.105 cm−1 (at Eγ of 1275 keV), raising the (Fe + Mn) concentration from 0.912 wt% to 11.214 wt%, as well as raising the soil samples density from 1.62 g/cm3 to 1.79 g/cm3. The study also shows an enhancement in the half value thickness, transmission factor, radiation protection efficiency and lead's equivalent thickness due to the enrichment of Fe + Mn concentrations within the studied soils. The results show that the Black cotton soil exhibits better shielding properties for γ-ray than the other soils.

The study focuses on creating new boro-silicate glasses doped with SnO2 for radiation shielding. It examines how substituting Na2O with SnO2 affects their structural, optical, and shielding properties. Density increases from 2.406 to 2.488 g/cm³ with rising SnO2, measured via the Archimedes Method. The examination for the glassy phase was performed using the XRD diffractometer. UV/Vis spectrophotometer analysis reveals reduced refractive index (2.412–1.976) and increased optical absorption-band gap (direct: 3.648–5.662 eV; indirect: 2.994–5.163 eV) with SnO2 concentrations of 0–9 mol.%). The effectiveness of the radiation shielding was assessed over the 0.059–1.408 MeV gamma-ray energy interval. The analysis demonstrates that when the concentration of SnO2 increases, the synthesized glasses' linear attenuation coefficient improves. As the SnO2 content was raised between 0 and 9 mol%, the linear attenuation coefficient rose between 0.489 and 2.892 cm−1 (at energy of 0.059 MeV) and between 0.126 and 0.128 cm−1 (at energy of 1.408 MeV), respectively. As the SnO2 content was raised between 0 and 9 mol%.

This work synthesized four glass samples with a fixed ratio of PbO to Na2O and a variable ratio of BaO to B2O3. The linear attenuation coefficient (LAC) (μ, cm−1) and additional attenuator parameters were determined experimentally using a semiconductor detector and different gamma sources. The comparison was carried out between the experimental and the XCOM calculated results, with good agreement emerging between the two results. The impacts of the BaO substituting for the B2O3 on fabricated PNBB glasses' radiation shielding properties were discussed. By increasing the BaO substitution concentration between 10 and 25 mol.%, the LAC μ values (cm−1) increased by 76.60 %, 13.81 %, 12.56 %, and 12.52 % for the respective γ-ray energies of 0.059, 0.662, 1.173, and 1.332 MeV. The μ value reduction with raised gamma energy values increased the values of the calculated half-value thickness (Δ0.5) as a result of the μ and Δ0.5 values' reverse proportionality. Other shielding parameters such as the lead equivalent thickness (Δeq) and radiation protection efficiency were also determined for the present PNBB glass samples.

The current study aims to develop new clay bricks doped with metallic waste for radiation shielding applications. The aforementioned new bricks were fabricated with various metallic waste concentrations under a pressure rate reaching ≈114 MPa and firing temperature of 1100 °C. The impacts of the metallic waste and the firing temperature on the developed brick samples' physical, radiation shielding, and structural properties were studied. In order to identify the fabricated bricks' mineral content, the X-ray diffraction pattern was used. Additionally, the fabricated bricks' porosity and density were experimentally determined, where the porosity was reduced by 28.03%, while their densities increased by ≈ 10.5% by raising the concentration of metallic waste. The linear attenuation coefficient (LAC) for the developed brick was investigated experimentally using a NaI (Tl) scintillation detector over the 0.033–1.408 MeV energy interval. The measured LAC values were enhanced by increasing the concentrations of metallic waste within the fabricated bricks over the examined energy interval. The fabricated brick's LAC enhancement improves the gamma-ray shielding characteristics. Therefore, the fabricated bricks are a cheap and suitable choice for radiation protection applications.

The current work aims to fabricate metal oxide-doped (PbO, Fe2O3, MgO, and Al2O3, each of which boasts a purity of 99%) zinc barium borate glasses through the melt quenching technique at the 1000 °C melting temperature. The results showed that adding 5 mol.% of metal oxides PbO, Fe2O3, Al2O3, and MgO increases the density of the zinc barium borate glasses. Additionally, the fabricated glasses' mechanical properties were determined based on the Makishima-Mackenzie model, which proved that the highest mechanical properties were achieved for glasses doped with Al2O3 compounds. The mechanical moduli for the glasses doped with Al2O3 reach 80.95 GPa (Young), 59.90 GPa (bulk), 31.75 GPa (shear), and 102.23 GPa (longitudinal). Additionally, the Al2O3-doped glasses' microhardness reaches 4.77 GPa. Moreover, estimation of the fabricated glasses' gamma-ray shielding capacity utilized Monte Carlo simulation. The highest linear attenuation coefficients are 29.132, 19.906, 19.243, and 18.923 cm−1 obtained at 0.033 MeV for glasses dopped by PbO, Fe2O3, MgO, and Al2O3, respectively. Therefore, glasses doped with 5 mol.% of PbO have high gamma-ray shielding capacities followed by glasses doped by Fe2O3.

The sintering process acquired ferromagnetic copper ferrite ceramic material with a small concentration of Ni ion at 1100 °C for 1 h. Previously, copper ferrite with Ni proportions powder was acquired by the wet chemical process according to the relation CuFe2-xNixO4 where x takes values 0.0, 0.015, 0.03, 0.04, and 0.05. The role of Ni ion in the copper ferrite structure was investigated by X-ray analysis, Scanning electron microscope, EDX analysis, and density measurements. The gamma-ray shielding properties for the fabricated CuFeNiO ceramics samples were evaluated using the Monte Carlo simulation method. The obtained results show an enhancement in the linear attenuation coefficient for the fabricated ceramics with increasing the insertions of Ni ions within the fabricated samples, where increasing the Ni ions concentration between 0 and 1.19 wt% increases the linear attenuation by between 1.581 and 1.771 cm−1 (at 0.103 MeV), 0.304–0.338 cm−1 (at 0.662 MeV), and 0.160–0.178 cm−1 (at 2.506 MeV), respectively. Simultaneously, the radiation protection efficiency for a 1 cm thickness of the fabricated samples increased between 14.8 and 16.3% with increasing the Ni ions between 0 and 1.19 wt%. Although the Ni doping concentration does not exceed 1.5 wt% of the total composition of the fabricated ceramics, the shielding capacity of the fabricated ceramics was enhanced by more than 11%, along the studied energy interval. Therefore, the fabricated samples can be used in gamma-ray shielding applications.

This research intends to recycle bone and incorporate it into concrete for radiation shielding application using Phy-X/PSD software. Cement, sand and granite were mixed in proportion of 0.5 kg:1 kg:1 kg to obtain sample A. Other concretes composing of cement, sand, granite and bone ash was in proportion 0.45 kg:1 kg:1 kg:0.05 kg, 0.1 kg:1 kg:1 kg:0.4 kg and 0.35 kg:1 kg:1 kg:0.15 kg to obtain samples B, C and D respectively. 0.5 water-to-cement (W/C) ratio was adopted throughout the mixes because the control mix contain the normal water quantity for normal hydration of cement. Replacing the bone ash for the cement in the fabricated concretes enhances their densities where the fabricated concretes' density decreased from 2.33 g/cm3 to 2.22 g/cm3 by raising the reinforcing bones fly ash concentration from 0 to 0.15 kg. Additionally, increasing the bones fly ash concentration within the fabricated concretes increases their linear attenuation coefficient (LAC) where the fabricated concretes’ μ values at 0.662 MeV reach 0.181 cm−1, 0.178 cm−1, 0.174 cm−1, and 0.171 cm−1,respectively for concretes A, B, C, and D. The use of other local materials is recommended, as it improves waste management being the major aim of the sustainable development goal.

A series of ordinary concrete is casted in order to examine the influence of the manganiferous siltstone rocks on the physical, mechanical, and gamma-ray shielding properties. Thus, a partial replacement for the coarse aggregates by siltstone rocks was performed during the fabrication of the currently ordinary concrete. The test revealed that raising the siltstone concentration improved the mechanical characteristics and density of the developed concretes. The addition of siltstone rocks at concentrations ranging from 0 to 40 wt% of the coarse aggregate concentration raises the density of the concrete from 2.05 g/cm3 to 2.3 g/cm3. Furthermore, partial substitution of basalt with siltstone rocks improves gamma-ray shielding properties. The experimental results for the linear attenuation coefficient show an increase in its value from 0.146 cm1 to 0.160 cm−1 when the siltstone concentration is increased between 0 and 40 wt% at 0.662 MeV. Furthermore, increasing the concentrations of siltstone affected the half-value thickness, which varied between 4.759 and 4.319 cm at 0.662 MeV. Therefore, the replacement presents a new alternative coarse aggregate that can enhance the mechanical and radiation shielding properties of ordinary concretes.

The present investigation aims to study the role of Pr2O3 on the structural, physical, and radiation shielding properties of a dense cadmium lead borate glass. The XRD was used to affirm the glassy amorphous structure of fabricated sample materials. Moreover, the FTIR was used to record the change in the FT-IR spectra due to the addition of Pr2O3 in the wavenumber interval between 400 and 4000 cm−1. The features of glass surfaces and the elemental analyses for the synthesized Pr2O3-reinforced cadmium lead borate glasses were performed using a SEM, supported by an energy-dispersive spectrometer. The γ-ray protection capacity was evaluated using the Monte Carlo method in a wide energy interval ranging between 0.015 and 15 MeV. The linear attenuation coefficient (LAC) at 1 MeV was reduced by a factor of 10 % from 0.372 cm−1 to 0.340 cm−1. The decrease in the LAC values negatively affected the other shielding properties such as half-value thickness and the transmission factor. Although the linear attenuation coefficient is decreased slightly with the partial substitution of CdO by Pr2O3 compound, the fabricated glass samples still have a high shielding capacity compared to the traditional commercial glasses as well as previous similar reported glasses.

The current study investigated Saudi Arabian oil fly ash impacts on Egyptian clay bricks' structural and radiation shielding properties. To produce the required bricks, crushed clay minerals from the Hafafit area were mixed with 0, 10, 20, 30, and 40 % wt.% Saudi Arabian oil fly ash and pressed at a pressure rate of 68.55 MPa. Identification of the minerals in the chosen clay was achieved via X-ray diffraction. Additionally, the material's morphology and chemical composition were determined through scanning electron microscope and energy-dispersive X-ray. The fabricated bricks' density was reduced by 36.3 % through increasing the concentration of fly ash from 0 to 40 wt%. Then, the fly ash addition's influence on the fabricated clay bricks' γ-ray shielding properties was investigated by Monte Carlo simulation, which found a reduction in the fabricated bricks' linear attenuation coefficient (LAC) by 41.2, 36.0, 33.8, and 33.8 % at the 0.059, 0.103, 0.662, and 1.252 MeV γ-ray energies, respectively. The LAC reduction caused an increase in the fabricated bricks' half-value thickness, transmission factor, and the equivalent thickness of the lead. Moreover, the thicker fabricated sample thicknesses were found to have high γ-ray shielding capacity and can thus be used in radiation shielding applications.

The effect of PbO addition with different concentrations on four synthesized zinc titanium borate glasses with the chemical formula xPbO-(75-x) B2O3-10ZnO-10BaO-5TiO2 (x = 30, 35, 40, and 45 mol%) was explored in this study. The partial PbO substitution for B2O3 increases the fabricated glasses' density by ≈ 20% from 5.31 to 6.37 g/cm3, respectively, with raising the PbO concentrations between 30 and 45 mol.%, respectively. Besides, the substitution mentioned above enhances the gamma-ray attenuation properties where the linear attenuation coefficient increased between 69.911 and 102.245 cm−1 (at 0.033 MeV), 0.341–0.415 cm−1 (at 1 MeV), and 0.200–0.262 cm−1 (at 10 MeV), increasing the PbO concentration between 30 and 45 mol.%, respectively. Simultaneously, increases in the PbO concentration within the fabricated glasses decrease the lead's equivalent thickness between 3.82 and 2.61 cm (at 0.033 MeV), 2.35–1.93 cm (at 1 MeV), and 2.81–2.14 cm (at 10 MeV). In contrast, substituting PbO for B2O3 compounds diminishes the fabricated glasses' mechanical properties, where the microhardness decreased by 13.5 % from 4.24 to 3.67 GPa. The lead equivalent thickness (Deq) values at 0.66 MeV were found equal to 2.410, 2.232, 2.078, and 1.945 cm, and at 1.112 MeV, these values were found equal to 2.222, 2.081, 1.956, and 1.829 cm for G1, G2, G3, and G4, respectively.

Composite materials based on a polymer matrix of linear low-density polyethylene (LLDPE) and W were produced by thermal pressing. The content of W in the samples varied from 0 to 70 %. The recycling properties of LLDPE are demonstrated in this study, which significantly helped to reduce the defects. The microstructure of the composites consists of well-defined W grains covered by elastic LLDPE fibers. A homogeneous distribution of tungsten in the polymer matrix was observed for sample W70. The EDX analysis showed the presence of tungsten and carbon (from the polymer component). The XRD analysis confirms the increase in W content in the samples. The FTIR spectra of the composites showed an increase in the content of terminal methyl groups, a decrease in the molecular weight, and a decrease in the degree of crystallinity of the polyethylene matrix with an increase in the W content in the composite. The sample with 70 % W content has the highest effective density (2.61 g/cm3). The sample relative density ranges from 93.3 to 97.7 %. The porosity of LLDPE-W composites does not exceed 7 %. Gamma radiation shielding efficiency parameters such as LAC, HVL, and MFP were calculated using Phy-X/PSD. The radiation source was Co60, with an emission range of 0.8–2.5 MeV. As the gamma energy increases, it is observed that the values of all the parameters deteriorate. However, the sample with a maximum W content of 70 % has the best values of LAC, HVL, and MFP among the other samples.

A unique brick series based on Vietnamese clay was manufactured at 114.22 MPa pressure rate for γ-ray attenuation purposes, consisting of (x) metallic waste & (90%-x) red clay mineral & 10% (hardener mixed with epoxy resin), where (x) is equal to the values 0%, 20%, 40%, 50%, and 70%. The impacts of industrial metal waste ratio in the structure and radiation protective characteristics were evaluated experimentally. The increase in metallic waste doping concentrations from 0% to 70% was associated with an increase in the manufactured brick's density (ρ) from 2.103 to 2.256 g/cm3 while the fabricated samples' porosity (Φ) decreased from 11.7 to 1.0%, respectively. Together with a rise in fabricated brick's density and a decrease in their porosities, the manufactured bricks' γ-ray attenuation capacities improved. The measured linear attenuation coefficient (μ, cm−1) was improved by 30.8%, 22.1%, 21.6%, and 19.7%, at Eγ equal to the values respectively 0.662, 1.173, 1.252, and 1.332 MeV, when the metallic waste concentration increased from 0% to 70%, respectively. The study demonstrates that manufactured bricks exhibit superior radiation shielding properties, with radiation protection efficiencies of 88.4%, 90.0%, 91.7%, 92.1%, and 92.4% for bricks with industrial metal waste contents of 0%, 20%, 40%, 50%, and 70%, respectively, at γ-ray energy (Eγ) of 1.332 MeV.

In the present work, a new brick series based on the Vietnamese white clay minerals from the Bat Trang was fabricated to be applied in the radiation protection applications during the decommissioning of the nuclear power reactors. The bricks were constructed under various pressure rates varied from 7.61 MPa to 114.22 MPa. The influence of pressure rate on the physical and γ-ray shielding properties were investigated in the study. The experimental measurement for the material's density using the MH-300A density meter showed an enhancement in the prepared bricks' density by 22.5 % with increasing the applied pressure rate while the bricks' porosity reduced by 31.2 % when the pressure rate increased from 7.61 MPa to 114.22 MPa. The increase in the fabricated bricks density and the reduction in their porosities enhances the bricks' linear attenuation coefficients as measured by the NaI (Tl) detector along the energy range extended from 0.662 MeV to 1.332 MeV. The linear attenuation coefficient increased by 13.8 %, 17.6 %, 17.0 %, and 17.1 % at gamma ray energies of 0.662 MeV, 1.173 MeV, 1.252 MeV, and 1.332 MeV, respectively. The enhancement in the linear attenuation coefficient increases the bricks' radiation protection efficiency by 10.22 %, 14.48 %, 14.09 %, and 14.26 % at gamma ray energies of 0.662 MeV, 1.173 MeV, 1.252 MeV, and 1.332 MeV, respectively.

The practice of identifying the potential zones for mineral exploration in a speedy and low-cost method includes the use of satellite imagery analysis as a part of remote sensing techniques. It is challenging to explore the iron mineralization of a region through conventional methods which are a time-consuming process. The current study utilizes the Hyperion satellite imagery for mapping the iron mineralization and associated geological features in the Irikkur region, Kannur, Kerala. Along with the remote sensing results, the field study and laboratory-based analysis were conducted to retrieve the ground truth point and geochemical proportion to verify the iron ore mineralization. The MC simulation showed for shielding properties indicate an increase in the linear attenuation coefficient with raising the Fe2O3+SiO2 concentrations in the investigated rocks where it is varied at 0.662 MeV in the range 0.190 cm−1- 0.222 cm−1 with rising the Fe2O3+SiO2 content from 57.86 wt% to 71.15 wt%. The analysis also revealed that when the γ-ray energy increased from 0.221 MeV to 2.506 MeV, sample 1 had the largest linear attenuation coefficient, ranging from 9.33 cm−1 to 0.12 cm−1. Charnockite rocks were found to have exceptional shielding qualities, making them an excellent natural choice for radiation shielding applications.

Hyperspectral data and its ability to explore the minerals and their associated rocks have a remarkable application in mineral exploration and lithological characterization. The present study aims to explore the radiation shielding aspects of the iron ore in Kerala with the aid of the Hyperion hyperspectral dataset. The reflectance-spectra obtained from the laboratory conditions as well as from the image show various absorptions. The results from the spectra are validated with geochemical data and GPS points. The Monte Carlo simulation employed to evaluate the radiation shielding ability. Raising the oxygen ions caused a noteworthy decrease in the μ values of the studied rocks which is accompanied by an increase in Δ0.5 and Δeq values. The Δ0.5 and Δeq values increased by factors of approximately 77 % with raising the oxygen ions between 44.32 and 47.57 wt.%. The μ values varies with the oxygen concentrations, where the μ values decreased from 2.531 to 0.925 cm−1 (at 0.059 MeV), from 0.381to 0.215 cm−1 (at 0.662 MeV), and from 0.279 to 0.158 cm−1 (at 1.25 MeV) with raising the oxygen ions from 44.32 to 47.43 wt.%.

Are borate and silicate glasses suitable for working as shieling materials against fast neutrons?To correctly answer the above question, some silicate, and borate-based glasses were fabricated and irradiated with various doses of fast neutrons varied between 1.73 and 12.10 MGy. The color and hardness of the fabricated glasses were affected by the fast neutron fluence where the transparent glasses turned colored as well as the hardness of the fabricated glasses was decreased. The gamma-ray spectrometric analysis shows a high activity concentration produced in the barium borate glasses due to the formation of radioisotopes Ba-131 and Ba-133 reaches to 5.92E+05 Bq and 4.25E+03 Bq, respectively for sample Cd-5 Batch 3. Additionally, the gamma-ray spectrometric analysis for the sodium silicate glasses shows low activity concentrations emitted from isotopes formed due to the activation of Y2O3-associated impurities. These activities are low compared to that emitted by barium borate-based glasses.

The present work aims to fabricate Na1+xZr2SixP3-xO12 compound at various calcination temperatures based on the zircon mineral. The fabricated compound was calcinated at 250, 500, and 1000°C. The effect of calcination temperature on the structure, crystal phase, and radiation shielding properties was studied for the fabricated compound. The X-ray diffraction diffractometer demonstrates that, the monoclinic crystal phase appeared at a calcination temperature of 250°C and 500°C is totally transformed to a high-symmetry hexagonal crystal phase under a calcination temperature of 1000°C. The radiation shielding capacity was also qualified for the fabricated compounds using the Monte Carlo N-Particle transport code in the γ-photons energy interval between 15keV and 122keV. The impacts of calcination temperature on the γ-ray shielding behavior were clarified in the present study, where the linear attenuation coefficient was enhanced by 218% at energy of 122keV, when the calcination temperature increased from 250 to 1000°C, respectively.

The synthetic B2O3As2O3 glass ceramic are prepared to investigate the physical properties and the radiation shielding capabilities with the variation of concentration of the As2O3 with 10, 20, 30, and 40%, respectively. XRD analyses are performed on the fabricated glass–ceramic and depicted the improvement of crystallinity by adding As2O3. The radiation shielding properties are studied for the B2O3As2O3 glass ceramic. The values of linear attenuation coefficient (LAC) are varied with the variation of incident photon gamma energy (23.1–103 keV). The LAC values enhanced from 12.19 cm−1–37.75 cm−1 by raising the As2O3 concentration from 10 to 40 mol% at low gamma energy (23.1 keV) for BAs10 and BAs40, respectively. Among the shielding parameters, the half–value layer, transmission factor, and radiation protection efficiency are estimated. Furthermore, the fabricated samples of glass ceramic have low manufacturing costs and good shielding features compared to the previous work. It can be concluded the B2O3As2O3 glass ceramic is appropriate to apply in X-ray or low-energy gamma-ray shielding applications.

The present work aims to optimize the radiation protection efficiency for ion-selective containers used in the liquid treatment for the nuclear power plant (NPP) cooling cycle. Some naturally occurring rocks were examined as filler materials to reduce absorbed dose and equivalent dos received from the radioactive waste container. Thus, the absorbed dose and equivalent dose were simulated at a distance of 1 m from the surface of the radioactive waste container using the Monte Carlo simulation. Both absorbed dose and equivalent dose rate are reduced by raising the filler thickness. The total absorbed dose is reduced from 7.66E-20 to 1.03E-20 Gy, and the equivalent dose is rate reduced from 183.81 to 24.63 μSv/h, raising the filler thickness between 0 and 17 cm, respectively. Also, the filler type significantly affects the equivalent dose rate, where the redorded equivalent dose rates are 24.63, 24.08, 27.63, 33.80, and 36.08 μSv/h for natural rocks basalt-1, basalt-2, basalt-sill, limestone, and rhyolite, respectively. The mentioned results show that the natural rocks, especially a thicker thickness (i.e., 17 cm thickness) of natural rocks basalt-1 and basalt-2, significantly reduce the gamma emissions from the radioactive wastes inside the modified container. Moreover, using an outer cementation concrete wall of 15 cm causes an additional decrease in the equivalent dose rate received from the container where the equivalent dose rate dropped to 6.63 μSv/h.

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.

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. Resumen: Se estudió el efecto de la sustitución de Pb2O3 por el contenido de CuO para el 75% de Li2B4O7 + (25 − x)Pb2O3 + xCuO sistema de vidrio donde x = 0, 5, 10, 15, 20 y 25% en peso. Se evaluaron las propiedades mecánicas y de protección contra la radiación para las muestras de vidrio investigadas. Las propiedades mecánicas incluidas Young, cizallamiento, volumen, longitudinal, relación de Poisson y microdureza se calcularon teóricamente en función del factor de empaquetamiento (Vi) y la energía de disociación (Gi) de los óxidos metálicos que constituyen las muestras de vidrio existentes utilizando el método Makishima-Mackenzie. modelo. Los resultados obtenidos muestran que la inserción de CuO mejora los diferentes parámetros mecánicos hasta en un 20% mol de los vidrios LBPCu investigados. Además, se estudiaron las propiedades de protección contra la radiación para el vidrio LBPCu investigado utilizando la simulación del código de transporte de partículas N de Monte Carlo (MCNP-5). Se utilizó MCNP-5 para detectar el coeficiente de atenuación lineal simulado (LAC) y luego el coeficiente de atenuación de masa (MAC) y otros factores basados en varias fuentes de rayos gamma con energías de 0,24, 0,66, 1,17, 1,33 y 1,40 MeV. Los resultados mostraron que el valor más alto de LAC disminuyó de 0,578 a 0,320 cm−1 para los vasos LBPCu0 y LBPCu25, respectivamente, a baja energía de 0,284 MeV. Además, se evaluaron los números atómicos efectivos y equivalentes (Zeff y Zeq), el factor de acumulación (EBF) y el factor de acumulación de absorción (EABF) para el vidrio LBPCu investigado utilizando el programa BXCOM. Los resultados revelaron que las propiedades de protección de los vidrios investigados mejoraron mediante la inserción de contenido de CuO.

In the current study, the PbO compound was used in order to optimize the gamma-ray shielding properties of the polypropylene polymers. A series of polypropylene doped PbO were performed using various PbO concentrations varied between 0 and 50 wt%. The experimental measurement for the density of the fabricated sample showed that the samples’ density varied between 0.902 ± 0.004 and 1.645 ± 0.007 g/cm3, raising the PbO doping concentration between 0 wt% and 50 wt%. Furthermore, the scanning electron microscope was utilized to illustrate the distribution and morphology of the fabricated polypropylene doped PbO concentrations. The gamma-ray shielding capacity of the fabricated polypropylene doped PbO was examined and evaluated experimentally using a sodium iodide scintillation detector and different point sources in the gamma-ray energy interval between 0.059 and 1.408 MeV. The experimental results were affirmed via the Geant4 code, which depended on the Monte Carlo simulation. The difference recorded between the experimental and Geant4 calculations for the fabricated samples shielding properties was lies in between ±4%. The recorded linear attenuation coefficient at gamma-ray energy of 0.244 MeV varied between 0.1148 and 0.5837 cm−1, raising the PbO doping concentration between 0 wt% and 50 wt%. Moreover, the half-value thickness decreased with increasing the PbO doping ratio.

The mechanical features evaluated theoretically using Makishima-Mackenzie's model for glasses xBaO-(50-x) PbO–50P2O5 where x = 0, 5, 10, 15, 20, 30, 40, and 50 mol%. Wherefore, the elastic characteristics; Young's, bulk, shear, and longitudinal modulus calculated. The obtained result showed an increase in the calculated values of elastic moduli with the replacement of the PbO by BaO contents. Moreover, the Poisson ratio, micro-hardness, and the softening temperature calculated for the investigated glasses. Besides, gamma and neutron shielding ability evaluated for the barium doped lead phosphate glasses. Monte Caro code (MCNP-5) and the Phy-X/PSD program applied to estimate the mass attenuation coefficient of the studied glasses. The decrease in the PbO ratio has a negative effect on the MAC. The highest MAC decreased from 65.896 cm2/g to 32.711 cm2/g at 0.015 MeV for BPP0 and BPP7, respectively. The calculated values of EBF and EABF showed that replacement of PbO with BaO contents in the studied BPP glasses helps to reduce the number of photons accumulated inside the studied BPP glasses.

Gamma radiation shielding features for three series of binary alloys identified as (Pb–Sn), (Pb–Zn), and (Zn–Sn) have been investigated. The mass attenuation coefficients (μ/ρ) for the selected alloys were simulated using the MCNP-5 code in the energy range between 0.01 and 15 MeV. Moreover, the (μ/ρ) values were computed using WinXCOM database in the same energy range to validate the simulation results. Results reveal a good agreement between the simulated and computed values. The half value layer (HVL), mean free path (MFP), effective atomic number (Zeff) and exposure buildup factor (EBF) were evaluated for the selected binary alloys. Results showed that the PS1, PZ1, and ZS2 alloys have the best shielding parameters and better than the commercially standard and available radiation shielding materials. Therefore, the investigated alloys can be used as effective radiation shielding materials against gamma ray with energies between 0.01 and 15 MeV.

Mechanical moduli, such as Young’s modulus (E), Bulks modulus (B), Shear modulus (S), longitudinal modulus (L), Poisson’s ratio (σ) and micro Hardness (H) were theoretically calculated for (100-x)TeO2+x MgO glasses, where x = 10, 20, 30, 40 and 45 mol%, based on the Makishima–Mackenzie model. The estimated results showed that the mechanical moduli and the microhardness of the glasses were improved with the increase of the MgO contents in the TM glasses, while Poisson’s ratio decreased with the increase in MgO content. Moreover, the radiation shielding capacity was evaluated for the studied TM glasses. Thus, the linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), transmission factor (TF) and half-value thickness (Δ0.5) were simulated for gamma photon energies between 0.344 and 1.406 MeV. The simulated results showed that glass TM10 with 10 mol % MgO possess the highest LAC and varied in the range between 0.259 and 0.711 cm−1, while TM45 glass with 45 mol % MgO possess the lowest LAC and vary in the range between 0.223 and 0.587 cm−1 at gamma photon energies between 0.344 and 1.406 MeV. Furthermore, the BXCOM program was applied to calculate the effective atomic number (Zeff), equivalent atomic number (Zeq) and buildup factors (EBF and EABF) of the glasses. The effective removal cross-section for the fast neutrons (ERCSFN, ∑R) was also calculated theoretically. The received data depicts that the lowest ∑R was achieved for TM10 glasses, where ∑R = 0.0193 cm2 g−1, while TM45 possesses the highest ERCSFN where ∑R = 0.0215 cm2 g−1.

Six borate and silica glasses with varying compositions were investigated for their mechanical and radiation shielding viability. Makishima-Mackenzie elastic model was utilized to study the elastic properties of the investigated glasses. The obtained results illustrated that PbO and Bi2O3 oxides reduced the glass samples' mechanical properties. For instance, the bulks' model decreased between 68.15 and 44.10 GPa, the shear model also followed the same trend and decreased from 31.95 to 23.33 GPa, reducing the PbO and Bi2O3 ratios in the studied glass samples. Monte Carlo N-Particle Transport Code (MCNP-5) was utilized to evaluate the investigated glasses' shielding capacity. The obtained results depict that the highest linear attenuation coefficient (LAC) occurred at 0.356 MeV; it takes values 0.618, 1.024, 1.161, 1.271, 1.963, and 2.071 cm−1 for G1, G2, G3, G4, G5, and G6. Based on the simulated values of LAC, other shielding properties such as transmission rate (TR), radiation protection efficiency (RPE), half-value layer (HVL) were evaluated. The calculated results illustrated that the shielding properties enhanced with Bi2O3 and PbO insertion ratios.

The mass attenuation coefficient μm for eight rock samples having different chemical composition was simulated using the MCNP 5 code in energy range (0.002MeV≤E≤10MeV). Moreover, the μm for the studied rock samples was computed theoretically using XCOM database. The comparison between simulated and computed data for all selected rock samples showed a good agreement with differences varied between 0.01 and 8%. The highest μm was found for basalt rocks M2 and M1 and the lowest one is reported for limestone rocks Dike. The simulated values of the μm then were used to calculate other important shielding parameters such as the mean free path, effective electron density and effective atomic number. The exposure buildup factor EBF was also computed for the selected rocks with the contribution of G-P fitting parameters and the highest EBF attended by the basalt sample Sill and varied between 1.022 and 744 in the energy range between (0.015≤E≤15MeV) but the lowest EBF achieved by basalt sample M2 and varied between 1.017 and 491 in the same energy range. Keywords: Gamma ray, Shielding properties, Natural rocks, MCNP, Buildup factor

Polyvinyl chloride (PVC) is the most widely produced synthetic plastic polymer in the world: it has a variety of applications due to its low cost, elasticity, light weight, good mechanical characteristics and corrosion resistance. In order to protect living beings from harmful radiation such as gamma rays, novel low-cost chalcocite and hematite-based PVCs were fabricated for shielding purposes. The mass attenuation coefficient μm for various fabricated hematite and chalcocite-based PVCs was calculated using MCNP-5 code. The results were compared with the values calculated theoretically using XCOM software between 0.015 and 15 MeV. Moreover, the simulated μm parameter for chalcocite/PVC and hematite/PVC was used to calculate other shielding factors, such as the half value layer (HVL), the mean free path (MFP) effective atomic number Zeff, the geometric-progress (G-P) fitting parameters and the exposure buildup factor (EBF). The simulated data of μm for all composites is comparable to that obtained from a theoretical calculation. The results showed that the addition of hematite and chalcocite enhance the μm of PVC polymers. We also found that the μm of chalcocite/PVC is higher than that of hematite/PVC due to the copper content in the former.

Elastic moduli were theoretically computed using the Makishima–Mackenzie model for SiO2–Na2O–CaO glasses doped with Sb2O3 contents. The calculated elastic moduli (Young’s, bulk, shear, and longitudinal modulus) were observed to increase with an increase in the Sb2O3 contents. The microhardness showed an increase, while Poisson’s ratio decreased with the rise of the Sb2O3 contents. In addition, gamma-ray and neutron shielding parameters were evaluated for the investigated glasses. The linear attenuation coefficient (LAC) was simulated using the Monte Carlo N-particle transport code (MCNP-5). Other parameters, such as the mass attenuation coefficient (MAC), transmission factor (TF), and half-value layer, were calculated based on the simulated LAC. The addition of Sb2O3 content was observed to enhance the investigated glasses’ shielding parameters, where the highest LAC was achieved for the SCNSb10 glass with 10 mol% Sb2O3 and decreased from 0.441 to 0.154 cm−1 at gamma energies between 0.248 and 1.406 MeV. Furthermore, the fast neutron effective removal cross-section (∑R) was computed theoretically. The calculated results showed that the highest ∑R was equal to 0.0341 cm2g−1 and was obtained for the SCNSb0 glass, which had no Sb2O3 content, while the lowest ∑R was equal to 0.0286 cm2 g−1 for the SCNSb10 glass sample. The present work was carried out to examine the advantages of the soda–lime glasses with different Sb2O3 contents in several photon shielding applications, especially for radiation safety in nuclear installations.