Radiation Shielding Materials Research Articles

Utilization of Waste Marble and Bi2O3-NPs as a Sustainable Replacement for Lead Materials for Radiation Shielding Applications

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 (LAC) values were measured experimentally through the narrow beam method at different energies (0.0595 MeV, 0.6617 MeV, 1.1730 MeV, and 1.330 MeV) for all samples with various concentrations of Bi2O3. Radiological shielding parameters such as half value layer (HVL), tenth-value layer (TVL), and radiation shielding efficiency (RSE) 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 HVL and TVL 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 HVLs. 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.

Development of HDPE/natural fiberboard nanocomposite reinforced Bi2O3/BaO and H3BO3: A sustainable approach for gamma and neutron shielding application

AbstractRadiation shielding materials significantly contribute to various fields. In this research, a new eco‐friendly nanocomposite shielding material based on high‐density polyethylene (HDPE) and natural fiberboard (NF) with different concentrations of barium oxide nanowires (BaO), bismuth oxide nanorods (Bi2O3), and boric acid (H3BO3) is constructed and investigated for 137Cs, 60Co gamma ray, and 142Am–Be neutron sources. Mechanical and physical testing and thermal analysis were conducted to assess the impact of nanostructure incorporation on the structural integrity and thermal stability of the nanocomposite. The 60Co gamma and neutron attenuation properties were evaluated using the appropriate radiation sources. The transmission and absorption coefficients of the nanocomposites were measured. The results demonstrated that HDPE/NF filled with BaO, Bi2O3 nanostructure, and boric acid has higher tensile strength and thermal stability than unfilled HDPE/NF. The results displayed that the HDPE/NF filled with 1.5% Bi2O3 and 1.5% BaO improved gamma attenuation and also HDPE/NF/10% boric acid had a high value. The outcomes of this research provide valuable insights into the design and fabrication of radiation shielding materials by understanding the relationship between nanoparticle concentration, radiation attenuation properties, and the mechanical and thermal characteristics of the nanocomposite. This study aims to optimize the performance and applicability of HDPE/NF nanocomposites for radiation protection applications.Highlights Synthesis of BaO nanowires and bismuth oxide (Bi2O3) nanorods by hydrothermal simple method. Fabrication and characterization of a new HDPE/natural fiberboard (NF) nanocomposite containing BaO/Bi2O3/H3BO3 as an eco‐friendly additive. The HDPE/NF/1.5% BaO/1.5% Bi2O3 nanocomposite has better tensile strength and more thermal stability. Usage of HDPE/NF/1.5% BaO/1.5% Bi2O3 nanocomposite that should be utilized for radiation shielding. Usage of HDPE/NF/1.5% BaO/1.5% Bi2O3/10% H3BO3 nanocomposite that should be utilized for neutron attenuation performance.

Enhancing gamma and neutron radiation shielding efficiency of LDPE/PVC polymers using cobalt, aluminum, and magnesium oxide fillers

A procedure for creating and assessing LDPE/PVC polymers using Co, Al, and Mg oxides as fillers for use as radiation shielding material was conducted. The SEM/EDX equipment was utilized for elemental analysis and mapping in order to visually represent the morphology of the produced polymers. The characterizations indicate that the MgCo2O4 particles possess an irregular and tiny morphology, displaying a spherical form with an average diameter of less than 100 nm. In addition, the Al2CoO4 particles are characterized as being aggregated, diminutive, and exhibiting a spherical morphology, with an average diameter of less than 150 nm. The current study involved experimental investigation, simulation using FLUKA-MC code, and theoretical calculations using Phy-X-PSD code to examine the radiological properties of the shielding material. The results depend on several factors, including the half-value layer (HVL), the effective atomic number (Zeff), the effective electron number (Neff), the effective conductivity (Ceff), the exposure buildup factor (EBF), the energy-absorption buildup factor (EABF), and the fast neutron macroscopic removal cross-section (FNRC). The SR-NIEL-7 platform has been utilized to compute the mass-stopping power for protons (H+) and alpha particles (He++) based on their kinetic energy. The experimental findings indicate that the density of LDPE/PVC filled with MgCo2O4 is greater than that of Al2CoO4. Furthermore, polymer filled with MgCo2O4 exhibits higher values for MAC, LAC, and FNRCs than Al2CoO4 filler. The measured LAC and MAC conform to the simulated values.

Radiation shielding properties of composites of TiZrNbHfTa refractory high entropy alloy reinforced with TiZrNbHfTaOx high-entropy oxide

Radiation shielding materials play a critical role in advancing the next generation of nuclear reactors. Among these, high-entropy materials with refractory properties emerge as a new category for radiation shielding applications. This study introduces TiZrNbHfTa-TiZrNbHfTaOx composites tailored for such purposes. Initially, a TiZrNbHfTa refractory high-entropy alloy (RHEA) is synthesized via mechanical alloying, followed by the oxidation of the alloy to obtain its refractory high-entropy oxide (RHEO), TiZrNbHfTaOx. Composites are then prepared by blending 5%, 10%, and 20% weight fractions of RHEO with RHEA using mechanical alloying. Comparative analysis of shielding properties reveals a decrease in mass attenuation coefficient and effective atomic number with increasing RHEO content. While RHEA exhibits superior shielding performance against gamma photons and neutrons, the composite containing 20% RHEO emerges as the optimal shield against alpha and proton irradiations. The equivalent neutron dose rate and removal cross-section values are obtained 49.8% and 0.142 for the composite with 20% RHEO, respectively. These findings, supported by computational simulations in this study, contribute valuable insights for the advancement of novel shielding materials crucial for future nuclear reactor technologies.

Impact of neodymium oxide (Nd2O3) substitution in barium–boron-phosphate glasses: A pathway to superior mechanical, optical, and radiation shielding performance

This study delves into the impact of substituting Nd2O3 for Na2O in Barium–Boron-Phosphate glasses, aiming to enhance their mechanical strength, optical characteristics, and radiation shielding efficacy. Glasses with a composition of 50B2O3 + 20P2O5 + 20BaO + (10-x)Na2O + xNd2O3 (x = 0, 1, 2, 3, 4 mol%) were synthesized and characterized. The findings indicate that as the Nd/Na ratio increases, the density of the glass also rises within the range of 3.77–4.23 g/cm3. Moreover, the addition of Nd leads to notable alterations in the optical characteristics of the resulting glasses. Specifically, there is a shift observed in the UV absorption edges, coupled with a noticeable increase in absorption at visible wavelengths. Moreover, Nd2O3 addition reduced the Urbach energy (from 0.6018 to 0.2239 eV for Nd0-Nd4) and the optical band gap indicating improved electronic structure and decreased disorder. The mechanical properties studied using the Makishima-Mackenzie model show As the replacement ratio of Nd2O3 increases, there is a noticeable improvement in the glass's mechanical robustness. Importantly, Glasses with high Nd/Na ratio in their composition exhibit enhanced radiation shielding capabilities, evidenced by increased mass attenuation coefficients and effective removal cross-sections for photons and fast neutrons, respectively. These findings suggest that Nd2O3-doped glasses offer a promising pathway for developing superior radiation shielding materials with tailored properties for diverse applications in nuclear facilities, medical devices, and space exploration equipment.

Advancing mechanical durability and radiation shielding properties in Silicon dioxide (SiO2) glasses through various incorporations: A comparative analysis

Silicon dioxide (SiO2) glasses, known for their high thermal stability, excellent optical transparency, and substantial mechanical strength, are crucial in numerous technological applications, including radiation shielding. This research explores the impact of compositional variations in SiO2-based glasses on their mechanical and radiation shielding properties, particularly focusing on the inclusion of heavy metal oxides (HMO) and rare earth elements (REE) like neodymium (Nd). Through the systematic investigation of fifteen distinct glass samples with varying concentrations of specific oxides and elements, we investigate the compositional changes and their influence on physical properties and their effectiveness in attenuating radiation. Our findings demonstrate that the incorporation of Nd significantly enhances the glass's radiation shielding capabilities. Glasses doped with Nd exhibited higher effective atomic numbers and electron densities, which translate to superior attenuation characteristics at lower photon energies. This is highlighted by the exceptional performance of the 20Nd sample, showing the lowest exposure build-up factors (EBF) at 10 mean free paths (mfp), indicating its potential as a premier candidate for shielding applications against various energy levels of radiation. Moreover, the variation in the Elastic Modulus of the glass samples underscores the significant impact of the glass matrix composition on its mechanical properties, suggesting a delicate balance between network formers and modifiers in determining the glass properties. It can be concluded that the neodymium-doped SiO2-based glasses may be considered as targeted compositions in fine-tuning material properties to meet specific application requirements. As the demand for efficient radiation shielding materials grows across medical, industrial, and space exploration sectors, our findings provide a solid foundation for the development of new glass formulations tailored for enhanced mechanical properties and superior radiation protection levels.

Analysis of high-energy radiation shielding features of SeTeSn glass after incorporation of bismuth

The main goal of this study is to evaluate how well several quaternary Chalcogenide Glasses (ChGs) shield against extremely intense radiation, such as X-rays and gamma rays. The ChGs under investigation are part of the quaternary glass system SeTeSnBi. By using the Phy-X/PSD program, it was possible to determine some important safety factors. We were specifically able to compute the linear/mass attenuation coefficients thanks to this software. Interestingly, we discover that these values are higher than those of several traditional and commercially available glasses, suggesting better-shielding characteristics. In addition, we investigated numerous important shielding characteristics, such as the removal cross-section, mean free path, transmission factor, half-value layer, and radiation protection efficacy. Furthermore, estimates have been made for the mechanical properties, such as the bulk modulus, shear modulus, longitudinal modulus, and Poisson's ratio. Examining the effects of substituting Bismuth atoms for Selenium atoms on the shielding capabilities of the original SeTeSn glass was a crucial component of our study. These thorough examinations offer insightful information on the possible uses of these quaternary ChGs as cutting-edge radiation shielding materials.

Simultaneous use of bismuth trioxide and mill scale for ternary blended geopolymer composite in radiation shielding applications

The present study evaluates Mill scale which is a steel industry waste and bismuth trioxide simultaneously as a potential radiation shielding material in geopolymer composite. An innovative and first of its kind lead-free design has been developed for making radiation shielding materials using mill scale and bismuth trioxide as shielding aggregates and industrial wastes such as fly ash and blast furnace slag as precursors for the geopolymer composite. The mill scale and bismuth trioxide based composite material are characterized for their radiation shielding characteristics based on shielding parameters commonly used in radiation shielding like linear attenuation coefficient (μ), half value thickness (HVT) and Mean Free Path (MVP) for 0.662 MeV energy. The determined shielding parameters are compared with traditional shielding materials like concrete with heavy aggregates. X-Ray diffraction studies have confirmed the presence of Bismuth ferrite as the major shielding phase responsible for radiation shielding. The mechanical properties of the prepared composites are determined for their strength in direct compression. Depending upon the radiation shielding parameters like linear attenuation coefficient and half value thickness an optimum dosage of mill scale and bismuth trioxide as a shielding composite to provide adequate shielding for X-Ray diagnostic and medical facilities against X-ray photons of low intensity has been recommended. The highest linear attenuation coefficient values of fly ash and slag based geopolymer composites had been observed to be 0.208 and 0.225, respectively.

Thermoplastic and thermoset polymer matrix composites reinforced with bismuth oxide as radiation shielding materials

Polymer composites reinforced with heavy metals have wide applications in the nuclear industry as radiation shielding materials against emitted radiation from nuclear equipment. In this study, considering bismuth oxide as reinforcement, various polymers including thermoplastic polymers, such as high-density polyethylene, low-density polyethylene, polypropylene, polyvinyl acetate, polymethyl methacrylate, and thermosetting epoxy resin have been considered as matrices. After preparing various samples of polymer composites loaded with 60 % by weight of bismuth oxide, some physical, mechanical, and radiation shielding properties (neutron and gamma attenuation coefficients) of these polymer composites have been measured and compared with each other. First, the density of the samples was measured, and the response of these samples to varying compressive force was investigated. The stress-strain diagrams of composites with different matrices were compared. Subsequently, the linear and mass attenuation coefficients of the composites were measured over a wide range of energies (32–1480 keV) against direct and collimated beams from various standard gamma-ray sources (134Cs, 60Co, 154Eu, 133Ba, and 22Na) using an HPGe detector. A collimated beam from an Am–Be source was utilized to measure and compare the attenuation properties of the composite samples against neutron flux. Furthermore, the properties of the composites against neutron and gamma radiation were calculated using the MCNP Monte Carlo code over a broad energy range, and the results were compared and validated with the experimental data. The comparison of the calculated and measured results shows reasonable agreement. The results indicate that in situations where high attenuation properties coupled with high strength are desired, polymeric composites with an epoxy matrix can be considered as radiation shielding materials. If the use of flexible and malleable material is required, such as for reactor piping shielding or the fabrication of protective gloves and clothing in a radiation environment, among the polymers studied, polyvinyl acetate is a more suitable matrix.

A Monte Carlo Simulation study on the Gamma Radiation Shielding Properties of Concrete with PET Plastic Composite using the PHITS Code

The gamma radiation shielding properties of four different types of PET concretes, containing 0 %, 5 %, 10 %, and 15 % PET additives, were simulated using the PHITS code. The simulation covered photon energy levels ranging from 0.01 to 1.5 MeV and employed a NaI (Tl) scintillation detector. Parameters such as the linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL), and mean free path (MFP) were calculated to evaluate the gamma-ray attenuation for each photon energy level. The effectiveness of PET plastics as a radiation shield depends on factors like material thickness, the type of radiation, and specific application requirements. However, this research provides valuable insights into repurposing waste PET plastics to enhance the radiation-shielding properties of concrete, contributing to improved waste management practices and the development of radiation-shielding materials. The results obtained from the PHITS code align satisfactorily with both the simulation results and the theoretical XCOM data.

Computing the gamma-ray, charged particles and fast neutron-shielding performances of selected alloys

Gamma-ray, charged particles and neutron-shielding properties of ternary alloy materials, (97.3 – x) Pb – x Cd – 2.7Ag (x = 10, 18 and 30) have been theoretically investigated. First, the effectiveness of gamma-ray shielding for the alloys was studied by using the Phy-X/PSD programme. Mass and linear attenuation coefficients (MAC and LAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic numbers (Zeff), effective electron densities (Neff) and effective conductivity (Ceff) were calculated for photon energy range 0.015–15 MeV. Second, the mass stopping powers (MSPs; dE/ρdx; MeVcm2/g) and ranges for electron, proton and alpha particle interactions were calculated at energy 0.01–20 MeV. Finally, the removal cross-section of fast neutron (FNRCS) for the alloys was calculated by the partial density method. Moreover, the neutrons and gamma-rays shielding effectiveness of ternary alloys were investigated using Monte Carlo (MCNP4b). The MCNP4b calculations were performed for neutrons in the energies 4 and 4.5 MeV. While the shielding parameters of gamma rays were done in the energy range of 0.015–15 MeV. The obtained results of radiation shielding showed that the P1 sample owns a good shielding effectiveness against neutrons and gamma rays compared to previously published studies. The comparison of the computed values has revealed a reasonable agreement between Phy-X/PSD and MCNP4b. This study gives essential data for potential applications of these materials in nuclear reactor core design and other industries for the evaluation of effective ionising radiation shielding materials.

Enhancement of Gamma-Ray and Neutron Shielding Properties of TeO2-Li2O-ZnO-Nb2O5 Glass System with the Addition of Sm2O3

Radiation shielding glass is widely used, as it protects people from ionizing radiation while allowing for the observation of irradiated areas. However, the performance of even the best-performing tellurite glass for radiation shielding still falls short compared to traditional radiation shielding materials. The effect of Sm2O3, with a high atomic number and cross section with neutron, on the gamma-ray and neutron shielding properties of a 75TeO2-5Li2O-10ZnO-(10-x)Nb2O5-(x)Sm2O3 glass system is studied in this work. Some critical shielding parameters, including linear attenuation coefficients, half-value thickness, tenth-value layer, and mean free path (MFP), have been calculated with the software Phy-X/PSD. Two kinds of gamma-ray buildup factors, the exposure buildup factor and the energy absorption buildup factor, have been calculated in the range of 0.015 to 15 MeV for depths up to 40 MFP. What’s more, their neutron shielding ability has been evaluated by calculating the neutron total effective removal cross section. It is shown that Sm2O3 promotes the gamma-ray and neutron shielding performance of the 75TeO2-5Li2O-10ZnO-10Nb2O5 glass system. The results indicate that the addition of Sm2O3 can be helpful for the radiation shielding performance of tellurite glass, which provides a practical way for designing glass with ideal shielding properties.

Evaluating the Effectiveness of Tellurium-Molybdenum Oxide Glass Systems for Radiation Shielding Protection

The present investigation examined TeO2–MeO3 glasses with different compositions for their ability to absorb γ-rays using the Phy-X and FLUKA Code, respectively. The study covered energies ranging from 0.015 to 15 MeV, where several parameters such as effective atomic number (Zeff), free path mean (GMFP), mass attenuation coefficient (GMAC), macroscopic cross-section (GLAC), and half-value levels were analyzed (GHVL). Glass composite composed of 80% TeO2 and 20% MoO3 was found to have the lowest GLAC content among the tested samples. GHVL = 0.055 cm was the half-value of the 80TeO2–20MoO3 glasses when they were subjected to 80 keV gamma-rays. It is anticipated that the GMFP of the investigated materials ranges from 0.004 to 0.005 cm when subjected to 100 keV gamma-rays. It was said that the increase in Zeff may be attributed to an increased quantity of electrons that were accessible for interaction with photons, resulting in a decreased probability of gamma rays passing through the shielding material. The cumulative impact of these findings demonstrates that specific glass compositions, particularly those that include Tellurium, have the potential to be used as excellent radiation shielding materials. These materials are becoming more important for providing efficient radiation protection in various industries and applications, including medical imaging, nuclear power, and space exploration.

Microstructure and radiation shielding properties of lead-fiber reinforced high-performance concrete

The increasing application of nuclear technology in medical fields has amplified the demand for radiation shielding materials. Traditional large-volume concrete cannot simultaneously exhibit excellent neutron and gamma-ray shielding capabilities while ensuring superior mechanical properties. This study tailored a novel lead fiber-reinforced high-performance concrete (LFRHPC) with lead fibers and magnetite aggregates, focusing on radiation attenuation. The effect of lead fibers on the mechanical performance, microstructure and radiation attenuation characteristics for LFRHPC was comprehensively evaluated. The results indicate a significant improvement in the mechanical performance of LFRHPC compared to traditional radiation shielding concrete (RSC), due to the scientific skeleton design. Additionally, the pore structure in LFRHPC is refined by incorporating lead fibers. Moreover, the interfacial transition zone (ITZ) between the cementitious matrix and magnetite is improved because of the very low water-to-binder ratio. To assess the radiation attenuation ability of LFRHPC, both direct measurements and simulation models were utilized. The data reveals that the porosity of LFRHPC plays a crucial role in its shielding effectiveness against neutron and gamma radiation. Furthermore, the addition of lead fibers considerably boosts its neutron and gamma-ray shielding attenuation capabilities. In summation, LFRHPC combines excellent mechanical properties and radiation shielding capabilities, making it suitable for construction applications in medical settings.

Exploring the metal tungstate oxides (MWO4; M = Ca, Sr, Ba, and Pb) as radiation shielding materials: a simulation study

Exploring the metal tungstate oxides (MWO4; M = Ca, Sr, Ba, and Pb) as radiation shielding materials: a simulation study

Synthesis and characterization of waste polyethylene/Bi2O3 composites reinforced with CuO/ZnO nanoparticles as sustainable radiation shielding materials

AbstractIn the present research, waste polyethylene (WPE)/Bi2O3 composites have been investigated as lightweight, inexpensive, and nontoxic lead‐free γ‐ray shielding materials. Different WPE‐based composites were prepared with varying concentrations of Bi2O3 (30 and 40 phr). The effect of adding ZnO and CuO nanoparticles (NPs) inside the WPE/Bi2O3 (30) matrix was studied by incorporating 10 phr of NPs inside it. The nanocomposites' structural, thermal, and mechanical properties and competence in shielding against γ‐radiation are studied. The outcomes revealed that the mechanical properties of the pristine WPE were enhanced after incorporating Bi2O3 by 30 phr, and then it worsened after increasing the Bi2O3 ratio to 40 phr. In contrast, better mechanical properties were obtained for those composites with NPs, where the maximum tensile strength (16.2 MPa) was recorded for the WPE/Bi2O3/CuO composite (higher than WPE by 47.27%). Numbers of parameters like μm, HVL (half‐value layer), TVL (tenth value layer), RPE%, and percentage of heaviness can denote the efficiency of shielding properties of composites at 662 KeV from 137Cs point source. It was found that μm and RPE% reach the maximum value for WPE/Bi2O3 (40 phr). Adding NPs decreases μm of WPE/Bi2O3 (30) slightly.Highlights Composites based on waste polyethylene (WPE)/Bi2O3 (30 and 40 phr) were fabricated. Nano CuO and ZnO improved the mechanical properties of WPE/Bi2O3 (30). WPE/Bi2O3 (40) composites show the best shielding characteristics. Nano CuO and ZnO slightly decreased μm of WPE/Bi2O3 (30).

Physical studies of chitosan/PEG loaded Fe2O3 nanoparticles microbeads as a based biodegradable material for radiation shielding

This work reports two different strategies for the formation of hybrid microbeads using chitosan and polyethylene glycol (PEG) as based biodegradable materials for radiation shielding. An organic–inorganic hydrogel was prepared by ionotropic gelation. During the in-situ loading, incorporating magnetic nanoparticles Fe2O3 into the polymer matrix, magnetic nanostructures, were entrapped in the polymer matrix during the physical cross-linking of the polymer with the physical cross-linker (sodium triphosphate). However, in case of post-loading mechanism the loaded nanoparticles favor the precipitation on the surface of the formed beads. We use different characterization techniques for our systems such as scanning electron microscopy (SEM), x-ray, infrared spectroscopy (XRD), and X-ray radiation shielding application. The results demonstrate that by incorporating nanostructured magnetic particles into the polymer matrix, the surface morphology based on the two processes allow the magnetic nanoparticles to be embedded or form an outer shell and precipitated on the surface of polymer microbeads. The values of μ for the hydrogels loaded with Fe2O3 by in-situ process have the larger values of the linear coefficient however, in case of post-loading process the values dramatically decrease in compare with the in-situ ones at the same tube voltage. The presented work recommended as a good mentor for radiation shielding.

Synthesis and analysis of composite comprising polybutylene succinate (PBS) and iodine contrast media for enhanced X-ray radiation shielding

ABSTRACT Within the field of radiology, safeguarding against radiation is crucial, particularly in diagnostic procedures like X-rays, as radiation exposure holds the potential to harm cellular DNA. Presently, lead serves as the predominant material for radiation shielding. However, its usage raises environmental concerns owing to its toxic properties. The objective of this study is to investigate a radiation shielding alternative to lead and assess its efficacy in protecting against radiation. We examined the radiation absorption properties of material made from a composite of PBS and iodine contrast media in various proportions. Our findings indicate that the shielding material containing 75% iodine have the greatest ability to reduce radiation dose from X-rays but are still less than lead. Moreover, the PBS composite with iodine contrast media proved to be environmentally friendly, flexible, and exhibited excellent shielding performance in mitigating exposure during diagnostic X-ray procedures.

Comprehensive study on structural, elastic and radiation shielding abilities of novel quaternary Bi2O3–TeO2–Li2O–Al2O3 glasses

Novel quaternary glasses with varying compositions of xBi2O3-(75–x)TeO2–20Li2O–5Al2O3 were synthesized using a melt-quenching method to analyze their physical, elastic properties and to evaluate their potential as radiation shielding materials. The X-Ray Diffraction (XRD), Fourier Transform Infrared (FTIR) and ultrasonic measurement were utilized to study those properties. The radiation shielding properties of the glass samples were determined for 0.01–10000 MeV photon energy range by using Phy-X/PSD software. The incorporation of Bi2O3, ranging from 0 mol% to 5 mol%, led to an increase in density which is measured by Archimedes' principle, ascending from 4.68 to 5.06 g/cm3. The longitudinal, bulk, shear, and Young's modulus, displayed a non-linear decline from 63.41 to 61.44 GPa, 33.52 to 33.20 GPa, 22.41 to 21.18 GPa, and 54.99 to 52.39 GPa. Furthermore, the inclusion of Bi2O3 up to x = 5 mol% produce mass attenuation coefficient (MAC) of 14.892 cm2/g at x-ray energy of 40 KeV, surpassing that of commercial RS360 and RS520 radiation shielding glasses by 577% and 323%, respectively. When subjected to gamma ray of 662 KeV the MAC is 0.08 cm2/g which was also accompanied by a reduction in the half-value layer (HVL) to 1.58 cm where it surpassed the concrete by 38% and linear attenuation coefficient (LAC) of 0.38 cm−1. The effective atomic number (Zeff) and effective electron density (Neff) reach maximum value of 59.74 and 7.88 × 1023 electrons/g at 0.02 MeV respectively. These results highlight the suitability of the glass composition with x = 5 mol% as an exceptional choice for employment as to shield against both X-rays and gamma rays.

Physical, Mechanical, and ionizing radiation shielding properties of 10PbO–10Na2O-(80-x)B2O3-xBaO glasses

This research explored the mechanical, physical, and ionizing radiation shielding properties of 10PbO–10Na2O-(80-x)B2O3-xBaO glass samples, where x = 10, 15, 20, and 25. The conventional melt-quench technique was employed to prepare the samples. The elastic moduli were investigated using the Makishima–Mackenzie model. At the same time, the radiation shielding properties involved a comprehensive analysis of the effective atomic number, linear attenuation and mass attenuation coefficients, half-value and tenth-value layers, radiation protection efficiency, and transmission factors, as well as the buildup factors for different mean-free paths (mfp). The impact of BaO (mol%) on the parameters mentioned above was investigated across a range of photon energies (0.015–15 MeV). In addition, the effect of BaO on the physical and mechanical properties of current glasses was studied. The addition of BaO showed an inverse impact on mechanical and physical properties, gradually reducing the glass's stability. In contrast, adding BaO to the compound enhanced photon attenuation ability, which means the sample with 25% BaO had the optimum capacity for radiation shielding amongst all the prepared samples. Moreover, the results demonstrated the complex interplay of Compton scattering, pair production, and the photoelectric effect, influencing the attention of photons. This work provides beneficial intuition into designing and optimizing glass-based radiation shielding materials.