WinXCom—a program for calculating X-ray attenuation coefficients

In this work, five tin alloys have been synthesized by rapid solidification process using melt-spun technique. Physical analysis demonstrates that, adding high density metals to tin alloy produces high density alloys between 6.99 and 8.9 g/cm³ and molar volumes between 12.7 and 19.17 cm³/mol. Utilizing Match 3's Rietveld refinement, the structural features of the prepared alloys were reported by X-ray diffraction. In terms of mechanical properties, the Sn-50Ag alloy found to have the greatest values of Young's modulus (184.5 GPa), tensile strength (470.2 MPa), yield strength (483.8 MPa), critical shear stress (12.3 GPa) and toughness (14.6 ×10⁶ J/m³) among all the prepared alloys. Using NaI(TL) scintillation detector and Co⁶⁰ and Cs¹³⁷point sources, gamma-ray linear and mass attenuation coefficients μ & μ_m, half-value layer (HVL) and mean free path (λ) were determined experimentally at three energy lines (0.667, 1.177 and 1.334 MeV). The measured μ_m values were compared with those estimated using WINXCOM software with good agreement between them. Various gamma-ray shielding parameters were estimated in the energy range between 0.015 MeV to 15 MeV using WINXCOM program. In comparison to other typical shielding materials and newly studied materials, the results show that the studied alloys are effective gamma shielding materials. The Sn-50Ag and Sn-50In alloys have the best mechanical efficiency with relatively good gamma-ray shielding performance. While the Sn-50Bi alloy found to have the best gamma-ray shielding performance with relatively good mechanical efficiency. As a result, the Sn-50Ag and Sn-50Bi can achieve a good balance between the shielding and mechanical performance and hence they are validated for radiation protection. The findings also show that, when compared to all other prepared alloys, common neutron shielding materials and recent studied materials, the Sn-50Ag has the best neutron absorption capability with Σ_R= 0.124 cm^-1. Finally, the Sn-50Bi alloy exhibits the best attenuation performance for protons (H⁺¹) and alpha particles (He⁺²) with regard to projected range (PR) and stopping power (MSP). These findings suggest that the Sn-50Ag and Sn-50Bi alloys make excellent nuclear shielding and mechanical performance for a variety of uses including the storage of nuclear waste, industrial and medicinal applications.

In this study, we employed 3D printing technology to fabricate poly lactic acid (PLA) polymer samples infused with gadolinium oxide nanoparticles at additive rates of 10% and 20%. The objective was to explore their potential as radiation shielding aprons within the medical X-ray and thermal neutron energy spectrum. To facilitate comparisons, a PLA polymer sample with no additive was also produced. The homogeneity and well-defined structures of the PLA samples were observed using SEM and EDS analyses. Additionally, the excellent thermal stability of the proposed test samples was reported. In terms of gamma-ray shielding, there is a remarkable consistency between experiment, theory and simulation outcomes with a maximum discrepancy of approximately 5%. P-PLA-Gd20 sample exhibits attenuation capabilities against X-rays to a level that could serve as an alternative to lead. Additionally, the thermal and fast neutron attenuation effectiveness of the prepared samples were determined. A shielding effectiveness of 100% against thermal neutrons was achieved using a 10 mm sample thickness and the P-PLA-Gd20 sample. The findings consistently highlight the efficacy of the proposed polymer sample with a 20% gadolinium oxide nanoparticle additive, positioning it as a viable and promising alternative to traditional lead aprons.

The research aims to exploring the gamma-ray shielding capacities of polyacrylonitrile/chrome-filled polymer composites through a combination of experimental, theoretical and simulation methods. Additionally, employing MCNPv6 and GEANT4 simulation tools, the study evaluates the materials' performance against neutron radiation. The materials were subjected to various gamma-ray energy levels, and their shielding efficacies are analytically quantified using parameters such as Radiation Protection Efficiency (RPE), Mass Attenuation Coefficient (MAC), Linear Attenuation Coefficient (LAC), and Half-Value Layer (HVL). At various neutron energies and sample thicknesses, the numbers of transmitted neutrons were evaluated. Notably, composite P0Cr50 (not contain polyacrylonitrile and containing 50% chromium) emerges prominently, demonstrating superior radiation shielding characteristics against both gamma and neutron radiations. This attitude is attributed to its optimal chrome dispersion and density, positioning it as a promising candidate for radiation shielding applications in industrial and nuclear domains.

In this study, Ni–Cu–Zn Fe₂O₄ ferrite nanoparticles have successfully been synthesized utilizing the Co-precipitation technique. The primary objectives encompassed elucidating phase purity, discerning functional groups, scrutinizing surface morphology, and conducting structural analyses. To accomplish these objectives, a battery of advanced characterization techniques was employed, including power X-ray diffraction, Transmission infrared spectroscopy, UV–Visible spectrophotometer, and Scanning electron microscopy. Furthermore, the investigation was extended to the assessment of the gamma ray shielding properties exhibited by the synthesized Ni–Cu–Zn Fe₂O₄ nanoparticles, spanning an energy range from 122 keV to 1330 keV. This evaluation was carried out through the utilization of a NaI(Tl) detector coupled with a PC-based multichannel analyzer. The acquired data were meticulously compared with established theoretical value. The results of this study point to a viable route for using this simple, cost-effective, and low-temperature synthesis approach to create nanomaterials suited for gamma ray shielding applications, as well as broader radiation protection. This novel technique has the potential to significantly improve radiation shielding technology. Along with this fast neutron attenuation capability of this prepared ferrite samples have been studied in terms of fast neutron removal cross section.

In the present study, the adaptable solution combustion synthesis is used to synthesize bismuth boron aluminum nanocomposites (BiBAl NCs) by using $Aloevera$ extract as a reducing agent. The as-obtained BiBAl NCs are characterized using conventional methods. Bragg’s reflections provided evidence that multi-phase BiBAl NCs with crystal diameters of 45 nm and 48 nm had formed. The surface structure of BiBAl NCs supported the aggregation of spherical nanoparticles. Using the EDAX spectrum, the existence of Bi, B, and Al was examined. According to calculations, the direct energy gap is 2.85 eV. Eventually, the X-ray and gamma radiation shielding properties are assessed using a NaI(Tl) detector linked with MCA. Standards for shielding are a bit higher than those for lead. Neutron shielding capabilities are contrasted with those of conventional shielding materials. The neutron attenuation properties and scattering length of BiBAl NCs are found to be efficient when compared to lead, concrete, and steel. The bremsstrahlung radiation shielding values are determined at 1.511 MeV. Bremsstrahlung efficiency is the same as lead, despite the fact that the bremsstrahlung dose rate and specific bremsstrahlung constant are determined to be higher. As a result, neutrons, bremsstrahlung radiation, and X/gamma rays may all be effectively absorbed by BiBAl NCs. Thus, the synthesized BiBAl nanocomposite can be used for Radiation shielding in place of toxic lead shielding.

The objective of this study was to examine the radiation protection capabilities of glass specimens with the composition xBaO: 1.5Dy₂O₃: 25ZnO: 5Al₂O₃: 30B₂O₃: (x-38.5)SiO₂ by varying x = 10 (Ba10) to 35 (Ba35) mol% of BaO concentrations. The glass specimens were fabricated using the melt-quenching technique. The results revealed that the physical and optical properties, such as density ($\rho$), molar volume (V_m), and refractive index (RI), had a similar trend. The % transmission result of glass specimens indicates higher transparency than those of commercial and x-ray windows. The experimental values of total attenuation (${\mu }_m$) in this study used the Compton scattering technique. The obtained results were then compared with theoretical calculation obtained from the WinXCom program and the PHITS (Particle and Heavy Ion Transport Code System) Monte Carlo simulation. The results indicated the values of ${\mu }_m$, effective atomic number (Z_eff), and electron density (N_eff) increase with the rise in BaO content. However, these values decrease at higher energy levels. The observed trends align with the theoretical predictions of the WinXCom program and the obtained results from the PHITS Monte Carlo simulation. The half-value layer (HVL) showed better shielding properties than both standard radiation shielding glass and other materials. Additionally, an examination of energy absorption (EABF) and exposure buildup factors (EBF) revealed a distinct advantage associated with the incorporation of BaO atoms. This advantageous effect was observed in the reduction of photon scattering events, further enhancing the overall efficacy of the shielding properties in the glass specimens under study.