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The purpose of this work is to prepare glass samples with the chemical formula xPbO 2 -23BaO-10CaO-(65-x)B 2 O 3 -2Y 2 O 3 (x = 10, 13, 16 and 19 mol%) using the usual melt quenching technique. These glasses are intended to be used as shielding materials designed to protect against ionizing radiation. Following the experimental measurement of the mass attenuation coefficient (G MAC ), which was done to explore the photon shielding capabilities of the prepared samples. The findings were then compared with the values that were estimated from the Phys-x database and simulated using Geant4 code. The experimental findings that were obtained demonstrated a satisfactory connection with the data that was obtained from both Phy-x and Geant4. Based on the observed G MAC , other radiation shielding characteristics were computed for each of the glass that were investigated. These parameters included the linear attenuation coefficient (G LAC ), the half-value layer (G HVL ), and the mean free path (G MFP ). Considering the data presented here, it seems that PBCBY-4 samples have the potential to be advantageous for use in shielding applications against ionizing radiation.

For technical and radioprotection causes, it has become essential to find new trends of smart materials which used as protection from ionizing radiation. To overcome the undesirable properties in lead aprons and provide the proper or better shielding properties against ionizing radiation, the tendency is now going to use ferrite as a shielding material. The co-precipitation method was utilized to prevent any foreign phases in the investigated MZN nano-ferrite. X-ray diffraction (XRD) and Fourier transmission infrared spectroscopy (FTIR) methods were used to analyze the manufactured sample. As proven by XRD and FTIR, the studied materials have their unique spinel phase with cubic structure Fd3m space group. The DC resistivity of Mg–Zn ferrite was carried out in the temperature range (77–295 K), and its dependence on temperature indicates that there are different charge transport mechanisms. The Mössbauer spectra analysis confirmed that the ferrimagnetic to superparamagnetic phase transition behaviour depends on Zn concentration. The incorporation of Zn to MZF enhanced the nano-ferrite density, whereas the addition of different Zn-oxides reduced the density for nano-ferrite samples. This variation in density changed the radiation shielding results. The sample containing high Zn (MZF-0.5) gives us better results in radiation shielding properties at low gamma, so this sample is superior in shielding results for charged particles at low energy. Finally, the possibility to use MZN nano-ferrite with various content in different ionizing radiation shielding fields can be concluded.

Bio-derived NiO-Carbon nanocomposites were prepared using Neem ( Azadirachta indica ) leaf extract through a green combustion approach. Structural analysis confirmed the formation of face-centered cubic NiO with crystallite sizes in the 25–50 nm range. The optimized 1:1 NiO: C composite demonstrated a limit of detection calculated via the 3σ/slope method in the millimolar range, along with a linear sensing response between 1 and 6 mM for glyphosate. In addition, the material achieved 98.78% degradation of Congo Red (CR dye) under UV irradiation (365 nm, 15 mW/cm²) while maintaining strong reusability and stability. The improved performance is attributed to the presence of conductive carbon, which facilitates charge transport, reduces electron–hole recombination, and increases the availability of active surface sites. Electrochemical impedance analysis further confirmed reduced charge-transfer resistance in the optimized composite, supporting its enhanced interfacial kinetics. The scalable and cost-effective synthesis, combined with stability in acidic media, highlights the potential of this composite as a multifunctional platform for pesticide monitoring and wastewater remediation.

The main objective of this work is to recycle unwanted industrial waste in order to produce innovative nanocomposites with improved mechanical, tribological, and thermal properties for use in various industrial purposes. In this context, powder metallurgy (PM) technique was used to fabricate iron (Fe)/copper (Cu)/niobium carbide (NbC)/granite nanocomposites having outstanding mechanical, wear and thermal properties. Transmission electron microscopy (TEM) and X-ray diffraction (XRD) examinations were used to investigate the particle size, crystal size, and phase composition of the milled samples. Additionally, it was investigated how different volume percentages of the NbC and granite affected the sintered specimens in terms of density, microstructure, mechanical and wear properties, and coefficient of thermal expansion (CTE). According to the findings, the milled powders included particles that were around 55 nm in size and clearly contained agglomerates. The results showed that the addition of 4 vol.% NbC and 8 vol.% granite nanoparticles caused a reduction in the Fe–Cu alloy matrix particle sizes up to 47.8 nm and served as a barrier to the migration of dislocations. In addition, the successive increase in the hybrid concentrations led to a significant decrease in the crystal size of the samples prepared as follows: 29.73, 27.58, 22.69, 19.95 and 15.8 nm. Furthermore, compared with the base Fe–Cu alloy, the nanocomposite having 12 vol.% of hybrid reinforcement demonstrated a significant improvement in the microhardness, ultimate strength, Young’s modulus, longitudinal modulus, shear modulus, bulk modulus, CTE and wear rate by 94.3, 96.4, 61.1, 78.2, 57.1, 73.6, 25.6 and 61.9%, respectively. This indicates that both NbC and granite can actually act as excellent reinforcements in the Fe alloy.

In this study, the monotonic effect of Ta2O5 and ZrO2 in some selected borotellurite glasses was investigated in terms of their impact on gamma-ray-shielding competencies. Accordingly, three niobium-reinforced borotellurite glasses (S1 : 75TeO2 + 15B2O3 + 10Nb2O5, S2 : 75TeO2 + 15B2O3 + 9Nb2O5 + 1Ta2O5, and S3 : 75TeO2 + 15B2O3 + 8Nb2O5 + 1Ta2O5 + 1ZrO2) were modelled in the general-purpose MCNPX Monte Carlo code. They have been defined as an attenuator sample between the point isotropic gamma-ray source and the detector in terms of determining their attenuation coefficients. To verify the MC results, attenuation coefficients were then compared with the Phy-X/PSD program data. Our findings clearly demonstrate that although some behavioral changes occurred in the shielding qualities, modest improvements occurred in the attenuation properties depending on the modifier variation and its magnitude. However, the replacement of 2% moles of Nb2O5 with 1% mole of Ta2O5 and 1% mole of ZrO2 provided significant improvements in both glass density and attenuation properties against gamma rays. Finally, the HVL values of the S3 sample were compared with some glass- and concrete-shielding materials and the S3 sample was reported for its outstanding properties. As a consequence of this investigation, it can be concluded that the indicated type of additive to be added to borotellurite glasses will provide some advantages, particularly when used in radiation fields, by increasing the shielding qualities moderately.

Erbium (III)- and terbium (III)-containing (1, 3 and 5 wt%) silicate-based bioactive glass powders were synthesized using sol–gel method. Their structural and physical properties were investigated. Radiation attenuation properties of the prepared glass samples were examined using Monte Carlo simulations. The photon transmission properties of the prepared bioactive specimens were obtained via Phy-X PSD program and FLUKA simulation. Results showed that all of the glasses synthesized in the study were amorphous. The true density values were measured in the range of 2.57–2.68 g/cm 3 . Simulation studies revealed that the lowest neutron cross section was observed for the pure 13–93 bioactive glass sample and the maximum neutron cross section was noted for the prepared bioactive specimens of 5% Er and 5% Tb. Bioactive glass powders synthesized in the study have potential to be used as radiation shielding material in tissue engineering applications.

A newly synthesized partially phosphorylated polyvinyl phosphate derivative (PPVP) was functionalized to extract Zirconium (IV) from Egyptian zircon sand. The specifications for the PPVP composite were approved effectively via different techniques, namely, FT-IR, XPS, BET, EDX, TGA, 1H-NMR, 13C-NMR, GC-MS, XRD and ICP-OES analyses, which demonstrated a satisfactory synthesis of PPVP and zircon dissolution from Egyptian zircon sand. Factors controlling parameters, such as pH values, shaking time, initial zirconium concentration, PPVP dose, nitrate ions concentration, co-ions, temperature and eluting agents, have been optimized. At 25 °C, pH 0, 20 min shaking, 0.05 mol/L zirconium ions and 0.5 mol/L nitrate ions, PPVP has an exciting preservation potential of 195 mg/g, equivalent to 390 mg/L zirconium ions. From the extraction–distribution isotherm, the practical outcomes of Langmuir’s modeling are better than the Freundlich model. With a theoretical value of 196.07 mg/g, which is more in line with the experimental results of 195 mg/g. The zirconium ions adsorption onto the PPVP composite follows the pseudo-second-order kinetics with a theoretical capacity value of 204.08 mg/g. According to thermodynamic potential, the extraction process was expected to be an exothermic, spontaneous and beneficial extraction at low temperatures. The thermodynamic parameters ΔS (−0.03 kJ/mol), ΔH (−12.22 kJ/mol) and ΔG were also considered. As the temperature grows, ∆G values increase from −2.948 kJ/mol at 298 K to −1.941 kJ/mol at 338 K. Zirconium ions may be eluted from the working loaded PPVP by 0.025M HNO3, with a 99% efficiency rate. It was found that zirconium ions revealed good separation factors towards some co-ions such as Hf4+ (28.82), Fe3+ (10.64), Ti4+ (28.82), V5+ (86.46) and U6+ (68.17). A successful alkali fusion technique with NaOH flux followed by the extraction with PPVP is used to obtain a high-purity zirconia concentrate with a zircon content of 72.77 % and a purity of 98.29%. As a result of this, the improved factors could finally be used.

High-density glasses of neodymio-cadmium lead borate of chemical composition xNd 2 O 3 /20CdO/20PbO/(57-x)B 2 O 3 /3Na 2 O, where (0 (0Nd) ≤ x ≤ 5 (5Nd) wt%) have been fabricated by a melt quenching process. Physical, structure properties as well as gamma-radiation and neutron shielding effectiveness in wide photon energy range 0.015–15 MeV have been examined. The amorphous nature of xNd-glasses was confirmed, where there was a lack of their crystallinity. Density was gradually increased from 5.006 g/cm 3 for 0Nd-glass sample to 5.245 g/cm 3 for 5Nd-glass sample. In terms of the mass attenuation coefficient (MAC), introducing Nd 3+ ions in the glass matrix has a direct constructive influence on the obtained values of MAC. Generally, the MAC trend follows the order (MAC) 5Nd  > (MAC) 4Nd  > (MAC) 3Nd  > (MAC) 2Nd  > (MAC) 1Nd  > (MAC) 0Nd . The linear attenuation coefficient (LAC) has a similar trend as MAC for all xNd-glasses. In terms of the half-value layer ( T 1/2 ), the 5Nd-glasses possessed the minimum T 1/2 values (0.004 cm at 15 keV to 4.301 cm at 15 MeV). Therefore, the T 1/2 of the fabricated xNd-glasses has an inverse behavior of the MAC and LAC. Thus, ( T 1/2 ) 0Nd  > ( T 1/2 ) 1Nd  > ( T 1/2 ) 2Nd  > ( T 1/2 ) 3Nd  > ( T 1/2 ) 4Nd  > ( T 1/2 ) 5Nd . The effective atomic number ( Z eff ) parameter follows the order ( Z eff ) 5Nd  > ( Z eff ) 4Nd  > ( Z eff ) 3Nd  > ( Z eff ) 2Nd  > ( Z eff ) 1Nd  > ( Z eff ) 0Nd . In the energies preferred for radiation applications, 5Nd-glasses possess very low exposure (EBF) and energy absorption (EABF) buildup factor values. The fast neutron removal cross-section (FNRC) of the fabricated glasses is improved as the Nd 3+ content increases in the glass matrix.

This study highlights the use of 89Zr-oxalate in diagnostic applications with the help of WinAct and IDAC2.1 software. It presents the biodistribution of the drug in various organs and tissues, including bone, blood, muscle, liver, lung, spleen, kidneys, inflammations, and tumors, and analyzes the maximum amount of nuclear transformation per Bq intake for each organ. The retention time of the maximum nuclear transformation and the absorbed doses of the drug in various organs and tissues are also examined. Data from clinical and laboratory studies on radiopharmaceuticals are used to estimate the coefficients of transition. The accumulation and excretion of the radiopharmaceutical in the organs is assumed to follow an exponential law. The coefficients of transition from the organs to the blood and vice versa are estimated using a combination of statistical programs and digitized data from the literature. WinAct and IDAC 2.1 software are used to calculate the distribution of the radiopharmaceutical in the human body and to estimate the absorbed doses in organs and tissues. The results of this study can provide valuable information for the biokinetic modeling of wide-spectrum diagnostic radiopharmaceuticals. The results show that 89Zr-oxalate has a high affinity for bones and a relatively low impact on healthy organs, making it helpful in targeting bone metastases. This study provides valuable information for further research on the development of this drug for potential clinical applications.