Gamma Radiation Attenuation Research Articles

Gamma radiation attenuation, mechanical properties and microstructure of barite-modified cement and geopolymer mortars

The present study contributes to the development of alternative materials for radiation shielding, focusing on environmental sustainability and material cost efficiency. The primary aim was to evaluate the compressive and flexural strength, mineral composition, microstructure, and gamma-ray attenuation properties of cement mortars and geopolymer mortars containing barite powder. Mortars based on ordinary Portland cement (OPC) and fly ash geopolymers with varying amounts of barite powder were assessed for their shielding properties at energy levels associated with the decay of 137Cs. From the results, key parameters such as the linear attenuation coefficient (μ), mass attenuation coefficient (μm), half-value layer (HVL), and tenth-value layer (TVL) were determined. The results showed that while cement-based composites exhibited superior gamma radiation attenuation compared to fly ash geopolymer mortars, the latter had higher mass attenuation efficiency, meaning less material density was required for the same level of shielding. Additionally, cement mortars had 23–25 % higher mechanical strength than geopolymer mortars. Importantly, the inclusion of barite powder improved the radiation shielding performance of both materials by 7–10 %, demonstrating its effectiveness in enhancing the protective properties of these mortars. This research highlights the potential of fly ash geopolymer mortars as viable, eco-friendly alternatives to traditional cement mortars in radiation shielding applications.

Graphene-based nanocomposites as gamma- and X-ray radiation shield

Commonly used materials for protection against ionizing radiation (gamma and X-ray energy range) primarily rely on high-density materials, like lead, steel, or tungsten. However, these materials are heavy and often impractical for various applications, especially where weight is a key parameter, like in avionics or space technology. Here, we study the shielding properties of an alternative light material—a graphene-based composite with a relatively low density ~ 1 g/cm3. We demonstrate that the linear attenuation coefficient is energy of radiation dependent, and it is validated by the XCOM model, showing relatively good agreement. We also show that the mass attenuation coefficient for selected radiation energies is at least comparable with other known materials, exceeding the value of 0.2 cm2/g for higher energies. This study proves the usefulness of a commonly used model for predicting the attenuation of gamma and X-ray radiation for new materials. It shows a new potential candidate for shielding application.

Evaluation of the protective properties and genotoxic potential of pyrazolo pyridine derivatives against neutron and gamma radiation using the Ames/Salmonella test system

Purpose Nuclear applications are being increasingly used in various fields, necessitating studies to protect from radiation hazards and their effects. In this study, five different chemical structures of pyrazolo [3,4-b] pyridine derivatives were synthesized. The gamma and neutron radiation protective abilities of these samples were determined and demonstrated their potential use as ingredients in radioprotective drugs. Material and methods Gamma radiation absorption parameters were calculated both theoretical and experimental. Important attenuation parameters for fast neutrons (4.5 MeV energy radiation) were figured out using the Monte Carlo simulation Geant4 code. Additionally, experimental dose rates were measured for each sample and compared to those of Paraffin and high-density polyethylene, an organic substance. Besides, Ames/Salmonella test system was aimed to detecting genotoxicity features of pyrazolo pyridine derivatives. Results All results demonstrated that each sample possesses both gamma and neutron radiation attenuation capabilities. It was determined that sample PPC4 (C20H14BrN5) exhibited the highest gamma radiation attenuation capacity among all samples, while sample PPC2 (C22H20N6) displayed an excellent neutron stopping capacity. The genotoxic properties of pyrazolo[3,4-b] pyridine derivatives were examined using the Ames/Salmonella test, and as a result, it was determined that these substances did not exhibit genotoxic effects at test doses up to 5 mM. Conclusion All obtained results indicate that all PPC (pyrazolo[3,4-b] pyridine derivatives) samples do not possess a toxic effect, and they can be utilized as an active substance for the development of a drug or cream with protective properties against both gamma and neutron radiations.

Effect of lanthanum oxide on the radiation-shielding, dielectric, and physical properties of lithium zinc phosphate glasses

This study looked at the shielding properties, physical properties, and dielectric spectroscopy of various lanthanum oxide concentrations based on (65-x) P2O5-15 Li2O–15ZnO– 5Bi2O3- xLa2O3 with x = 0.0, 1.0, 2.0, 3.0, and 4.0 mol% glasses. When La2O3 is added, the molar volume quantities fall but the density values increase. The sample with the designation La-4.0 (4.0 mol% La2O3 content) had the highest density observed, 3.2182 g/cm3. Monte Carlo simulations and the Phy-x/PSD software were used to determine the critical gamma radiation attenuation characteristics, particularly linear attenuation coefficients and mass attenuation coefficients of glass samples under investigation. The half-value layer, mean free path, effective atomic number and effective electron density were then examined across a wide energy range (0.015–15 MeV). The findings of the investigation showed that the addition of La2O3 decreased the half-value layer and mean free path while increasing the mass attenuation coefficient, effective atomic number, and effective electron density. The results indicate that the inclusion of La2O3 appears to improve that glass system's ability to deflect gamma and neutron radiation. Over a broad frequency range, the dielectric properties were measured. The dielectric constant (ε′), which is typically steadily decreased with the addition of lanthanum, indicates an increase in the degree of electrical stiffness inside the glass network. Among the samples examined, the glass sample La-4.0 is thought to possess the best properties for electronic packaging due to its maximum propagation speed and lowest dielectric constant.

Enhancing mechanical and radiation shielding properties of concrete with lead monoxide and granodiorite: Individual and synergistic effects at micro and nano particle scales

AbstractThis study investigates the individual and combined effects of micro and nano lead monoxide (PbO) and granodiorite (GD) on concrete's mechanical and radiation shielding properties. Both materials were partially substituted for cement at varying ratios. Additionally, mixtures with optimal radiation shielding performance were prepared to explore the synergy of combining them. The mentioned materials are used for the first time in an extensive study at the nano scale to investigate their impact on concrete's mechanical properties, microstructure, and gamma radiation attenuation. Two gamma ray sources of uranium (U238) and cesium (Cs137) were used measure the radiation attenuation coefficients for all designed concrete mixes. A simple methodology was followed to assess the concrete shields efficiency via utilizing portable handheld gamma‐ray spectrometer that offers two reading modes. Results indicated that increasing the ratio of PbO is directly proportional to the concrete ability to attenuate radiation, where the optimal individual replacement ratios were recorded at 5% for micro and nano particle sizes. At this ratio, the linear attenuation coefficient (μ) values were improved by 39.57% and 24.78% for the nano and micro PbO, respectively. Additionally, the optimal ratio for improving mechanical properties was at 3% and 2% for nano and micro PbO, while the higher ratios showed a decline in mechanical properties especially at 5% micro PbO with 7.02% reduction in the compressive strength value. Regarding GD powder, the optimal replacement ratios for improving concrete radiation shielding were consistent with those enhancing its mechanical properties at 4% and 7% in both nano and micro scales, respectively. The combined mixes further enhanced the overall concrete performance, especially its radiation shielding ability. Compared to the control mix, the compressive strength, tensile strength, and μ were increased by 25.7%, 16.2%, and 44.7% at the optimal mixture of 5% nano PbO + 4% nano GD.

Examining Low-Energy Gamma-Ray Protection of a New Promising Saudi Cement Product as Alternative Cementitious Material Using Geant4 Software

In modern life, cement products have become an essential material for the foundations in many structural building designs. Because of this, the natural effects of this material need to be tested and cannot be ignored. Modeling interactions of gamma rays with several cementitious compounds is the focus of this study. Gamma radiations exist naturally and artificially, but with limited gamma-ray energies, which are not easy to access for experimental gamma attenuation studies. So in the current work, a wide range of low gamma-ray energies (0.01 to 0.356 MeV) are applied to investigate the gamma radiation attenuation properties theoretically for different cement materials. Also, the Monte Carlo statistical method is applied using the Geant4 toolkit to simulate the results. The outcomes are compared with theoretical values using XCOM to validate at these energies. The effective atomic number ( Z eff ), electron density ( N eff ), and half-value layers (HVLs) for the studied samples are computed based on the simulated mass attenuation coefficient ( μ m ), as expected. The outcomes show good agreement between the simulated results with those calculated theoretically by XCOM within an 11% deviation. The silica fume sample showed a slightly higher μ m value compared with the other samples. The dependence of the photon energy and cement composition on the values of the μ m and HVLs are investigated and discussed. In addition, the values of Z eff and N eff for all cement samples behaved similarly in the given photon energy range, and they decreased as the photon energy increased.

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.

Enhancing radiation shielding transmission factors and mechanical Robustness of borosilicate glasses through Bi2O3 modification: A comprehensive study

The mechanical behavior and gamma radiation attenuation features of borosilicate glasses with chemical compositions 16ZnO–8BaO-5.5SiO2-0.5Sb2O3-(70-x)B2O3/xBi2O3 are extensively investigated. Makishima-Mackenzie principle, Monte Carlo code, and Phy-X/PSD software are utilized in terms of determining these properties. Our results showed that the total packing density (Vt) decreased from 0.634851 to 0.571458, while the total dissociation energy increased from 26.612 (kJ/cm3) to 29.652 (kJ/cm3) for S1-glass (with 10 mol% of Bi2O3) and S5-glass (with 30 mol% Bi2O3). All elastic moduli are enhanced by increasing the Bi2O3 additive in the investigated glasses. Poisson's ratio was decreased from 0.281226 for S1-glass to 0.256957 for S5-glass. In terms of gamma-ray shielding parameters; linear (μ) and mass attenuation (μm) coefficients for the rich glass sample with B2O3 (S5) possess the highest values among all investigated (S1–S5) samples. The glass sample S5 is reported with the lowest values of tenth (TVL) and half (HVL) value layers among all studied glasses. In addition, the exposure (EBF) and energy absorption (EABF) bulidup factors were decreased with increasing the amount of Bi2O3 reinforcement for mean free path values from 0.5 to 40 mfp. The lowest possible levels of attenuation (minimum transmission) were measured at a thickness of 3 cm for all of the glass samples.

Design and Study of Novel Composites Based on EPDM Rubber Containing Bismuth (III) Oxide and Graphene Nanoplatelets for Gamma Radiation Shielding.

The mechanical, thermal and gamma radiation attenuation properties of ethylene-propylene-diene monomer (EPDM)-based composites containing graphene nanoplatelets (GNs) and bismuth (III) oxide nanoparticles (B) were investigated. The use of polyethylene glycol (PEG) as a compatibilizer to improve the dispersion of the fillers was also investigated. The results showed that the combined use of these fillers resulted in a drastic increase in mechanical properties, reaching 123% and 83% of tensile strength and elongation at break, respectively, compared to those of EPDM. In contrast, the addition of PEG to composites containing EPDM GNs and B resulted in composites with lower values of mechanical properties compared to the EPDM/B/GN-based composite. However, the presence of PEG leads to obtaining a composite (EPDM/B/GNP) with a mass attenuation coefficient to gamma radiation (137Cs, 662 keV) superior to that composite without PEG. In addition, the composite EPDM, B and PEG exhibited an elongation at break 153% superior to unfilled EPDM. Moreover, the binary filler system consisting of 100 phr of bismuth (III) oxide and 10 phr of GN leads to reaching 61% of the linear damping coefficient of the EPDM composite compared to that value of the unfilled EPDM. The study of the morphology and the state of filler dispersion in the polymer matrix, obtained using scanning electron microscopy and energy-dispersive X-ray spectroscopy, respectively, provides a useful background for understanding the factors affecting the gamma radiation attenuation properties. Finally, the results also indicated that by adjusting the formulation, it is possible to tune the mechanical and thermal properties of EPDM composites reinforced with bismuth oxide and graphene nanoplatelets.

Effect of the Elemental Composition of Optical Glasses on the Quantitative Characteristics of X-Ray and Gamma Radiation Attenuation

Effect of the Elemental Composition of Optical Glasses on the Quantitative Characteristics of X-Ray and Gamma Radiation Attenuation

Studies of gamma radiation attenuation properties of silica-based commercial glasses utilized in Jordanian dwellings

Studies of gamma radiation attenuation properties of silica-based commercial glasses utilized in Jordanian dwellings

Enhancing Radiation Shielding with Gadolinium(III) Oxide in Cerium(III) Fluoride‐Doped Silica Borate Glass

This study investigates the radiation shielding properties of glass samples within the xGd2O3‐5SiO2‐40Na2O‐(54.5‐x) B2O3:0.5CeF3 composition, where x varies from 0 to 10 mol.%, which is coded as GSNBCX (X = 1, 2, 3, and 4). The assessment is done through comprehensive Monte Carlo simulation and Phy‐X/PSD software analyses. The primary objective of this study is to comprehensively evaluate the radiation shielding properties of glass compositions with varying Gd2O3 concentrations. This evaluation encompasses both the attenuation of gamma radiation within the broad energy range of 0.015 MeV to 15 MeV and the assessment of fast neutron removal cross sections, with a specific focus on simulations spanning energy levels from 0.5 to 10 MeV. By examining these parameters, we aim to elucidate the impact of Gd2O3 concentration on the material’s overall effectiveness in radiation shielding applications. The results reveal a significant variation in the mass attenuation coefficient (μm) across the investigated glass samples. For instance, μm values range from 3.244 to 0.019 cm2·g−1 for GSNBC1, 20.471 to 0.025 cm2·g−1 for GSNBC2, 27.245 to 0.027 cm2·g−1 for GSNBC3, and 32.223 to 0.029 cm2·g−1 for GSNBC4. Notably, GSNBC4, characterized by a substantial Gd2O3 concentration (10 mol.%), exhibits the highest values of both μm and linear attenuation coefficient (μ). Furthermore, the investigation delves into the fast neutron removal cross section (FNRCS), which displays values of 0.97, 0.95, 0.094, and 0.93 cm−1, respectively. GSNBC1, marked by its elevated B2O3 content (54.5 mol.%), showcases the highest FNRCS. These findings underscore the efficacy of Gd2O3‐doped materials in shielding against gamma rays, holding promise for various applications in radiation protection, particularly in the medical and nuclear sectors. This study contributes valuable insights into developing effective radiation‐blocking materials for diverse industrial and scientific contexts.

Gamma radiation for the estimation of mineral soil water content in a boreal forest

Continuous monitoring of water quantities in different soil horizons is necessary to understand the behavior of infiltrated water in the soil. Under certain conditions, using measurements of natural ground gamma radiation can help us estimate soil water content measurements over a 100 m2 surface within a 15 cm depth. A CS725 sensor can provide up to four daily estimates of soil water content by detecting the natural emission of gamma radiation. However, in boreal forest environments, gamma radiation mitigated by the water in the thick humus layers (litter, fermented, and humic horizon) can bias the underlying mineral soil water content measurements. The objective of this research was to evaluate the accuracy of methods that incorporate variables describing the surface humus layer into calculations of the underlying mineral soil water content, by measuring the soil’s natural gamma emission with the CS725. Using raw gamma radiation values obtained by CS725 sensors deployed over various boreal soils, we tested two functions. The first one included variables describing the humus layer and the other excluded these variables (manufacturer’s method). The function that included the descriptive humus layer variables showed superior results compared to the function without. The results of this study suggest that the CS725 sensor can adequately estimate mineral soil water content within ±10% absolute of the reference water content when examined with the following humus variables: humus layer thickness, fractioned composition, bulk density, and linear gamma radiation attenuation.

Effect of colemanite mineral on gamma radiation attenuation properties of vinyl ester resin

In this study, it is aimed to experimentally and theoretically obtain the gamma radiation attenuation properties of vinyl ester resin (VE) containing different rates of colemanite (CO) mineral and to compare these results. In the first stage, experimental measurements were performed using a gamma spectroscopy system containing a NaI(Tl) detector at three different gamma energies (511, 835 and 1275 keV) emitted from two different radioactive sources (22Na and 54Mn). As a result of the experiments, linear attenuation coefficients (LACs) of VE samples were obtained. The variation of LACs according to the density of the samples were investigated. The obtained results showed that LACs increased the density of the VE samples increased. Using the experimental LAC results, the half (HVL) and tenth (TVL) value layer thickness, mean free path (MFP) and transmission rate values were calculated. In the second stage of the study, LACs were calculated theoretically with the help of XCOM code using the chemical contents of VE samples. As a result of the comparison of the LACs obtained experimentally and using the XCOM code, it was observed that they were in good agreement. In addition, the results obtained with the XCOM code gave information about the variation of the attenuation coefficient in different energy regions. Based on all these data, it was concluded that as the amount of colemanite in the vinyl ester resin examined in the study increased, the gamma radiation shielding performance increased.

Electrospun PVDF/Barium hexaferrite fiber composites for enhanced electromagnetic shielding in the X-band range

In the contemporary, digitally–driven era, the prevalence of electronic devices has drastically escalated electromagnetic (EM) pollution levels, marking a significant environmental challenge. Electrospun fiber composites of polyvinylidene fluoride (PVDF) and Barium hexaferrite (BHF) were analyzed for their potential usage in X-band electromagnetic shielding applications (EMSAs). Pure PVDF and BHF-PVDF fiber composite were manufactured by needleless electrospinning. X-ray diffraction (XRD), Fourier-transform infrared spectroscopy (FTIR), scanning electron microscopy (SEM), thermogravimetric analysis (TGA), vibrating sample magnetometer (VSM), and EM measurements utilizing a vector network analyzer (VNA) are all used to describe the prepared samples. The XRD and FTIR analyses confirmed the successful incorporation of BHF into the PVDF matrix. The results show that adding PVDF to BHF in fiber form enhances the reflection loss (RL), indicating improved electromagnetic shielding effectiveness (EMSE). The SEM analysis revealed that the fiber composite had a uniform fiber diameter distribution. In contrast, the TGA analysis demonstrated good thermal stability of the fiber composite. Polymer samples were evaluated to enhance gamma radiation and neutron particle attenuation. MCNP5 and Phy-X/PSD software were used to study semi-crystalline fluorocarbon polymer (PVDF) and barium hex ferrite BaFe12O19 (30 wt%) with PVDF (70 wt%). The MCNP5 programme simulated 0.015–15 MeV radiation attenuation. Additionally, the Phy-X/PSD programme verified the simulated µ values for the chosen Mxenes materials. The MCNP-5 code and Phy-X/PSD results were agreed. The linear attenuation coefficients for the polymer samples ranged from 3.166 to 0.032 cm2.g−1 for PVDF and from 73.960 to 0.113 cm2.g−1 for PVDF and BHF-PVDF Fiber at photon energies from 0.015 to 15 MeV. Overall, the electrospun fiber composite of PVDF and BHF particles shows promise for EMSAs in the X-band range. The enhanced RL observed in our study suggests that these fiber composites could be used to protect against electromagnetic radiation (EMR) from electronic devices, which is increasingly concerning in today's modern society.

Attenuation of Neutron and Gamma Radiation from a Reactor by Metal-Hydride Shielding

Attenuation of Neutron and Gamma Radiation from a Reactor by Metal-Hydride Shielding

Gamma radiation shielding properties for polymer composites reinforced with bismuth tungstate in different proportions

In this study, inorganic compound (Bi2(WO4)3) was added into the composite to improve the radiation shielding properties of polymer composite. A polymer matrix was prepared by combining unsaturated polyester resin with methyl ethyl ketone peroxide and cobalt octoate (6%), and Bi2(WO4)3 was added to this polymer matrix at different ratios as filling material. In order to investigate the gamma radiation attenuation properties of the obtained polymer composites, mass attenuation coefficients, radiation shielding efficiencies, radiation transmission factors, linear attenuation coefficients, half values layer, tenth values layer, mean free path values, effective atomic numbers and effective electron densities parameters were obtained. Experimental studies were carried out with the help of HPGe detector at 22 different energies emitted from 22Na, 54Mn, 57Co, 60Co, 133Ba, 137Cs, 152Eu and 241Am radioactive sources in the photon energy range of 59.5–1408.0 keV. Each obtained experimental result was compared with the theoretical results. It was observed that the sample encoded with BiWO20 is the best radiation shielding material among all studied composites (except 59.5 keV).

Elucidating of the influence of tin and cadmium in the Bi–Pb alloy on its thermal and nuclear properties as a coolant in fast neutron reactors

The purpose of this research is to investigate the physical properties and shielding characteristics of prepared (Bi–Pb) and (Bi–Pb–Sn–Cd) alloys, to be used as a coolant in a liquid metal nuclear fast reactor. The physical properties density, kinetics and mechanism of melting applying the reverse Johnson–Mehl–-Avrami rule and reduced time plot were applied, showing that melting processes take place in two dimensions, enthalpy and heat capacity were measured on the other hand for the prepared alloys within the solid and liquid states, respectively. Moreover, the results indicated that the bulk density and melting temperature of (Bi–Pb–Sn–Cd) alloys are lower than (Bi–Pb) alloys. Likewise, the thermal properties of (Bi–Pb–Sn–Cd) alloys seemed more suitable applicants than that of (Bi–Pb) alloys. Additionally, eight different gamma-ray energy lines in the range 0.12178–1.40792 MeV were used to determine the mass attenuation for the alloy samples. Also, gamma radiation attenuation characteristics, the half-value layer and effective atomic number were determined using Phy-x/PSD software. Furthermore, three types of neutron energies (slow neutrons, total slow neutrons, as well as neutrons of energies greater than 0.4 eV) were used to determine the macroscopic neutron cross-sections for the prepared alloys. The calculated values of mass attenuation coefficients exhibited a very good agreement with the experimental values of those parameters. The values of neutron macroscopic cross sections at fast neutrons for (Bi–Pb) and (Bi–Pb–Sn–Cd) alloys are small, this means that there is no consequence on fast neutrons used in a nuclear breeder reactor. Finally, we may reach the conclusion that Bi–Pb–Sn–Cd alloys are a possible candidate to be used as a coolant in fast nuclear reactors, as well as it is most suitable as an outer cooling and shielding blanket vessel as well.

Impact of Growth Temperature of Lead-Oxide Nanostructures on the Attenuation of Gamma Radiation.

Chemical bath deposition (CBD) technique is utilized to grow lead-oxide (PbO) nanostructures (NSs) over PbO seed fabricated by physical vapor deposition (PVD) method on glass substrates. The effect of growth temperatures 50 and 70 °C on the surface topography, optical properties, and crystal structure of lead-oxide NSs has been studied. The investigated results suggested that the growth temperature has a huge and very considerable influence on the PbO NS, and the fabricated PbO NS has been indexed as the Pb3O4 polycrystalline tetragonal phase. The crystal size for PbO thin films grown at 50 °C was 85.688 nm and increased to 96.61 nm once the growth temperature reached 70 °C. The fabricated PbO nanofilms show a high rate of transmittance, which are ∼70 and 75% in the visible spectrum for the films deposited at 50 and 70 °C, respectively. The obtained Eg was in the range of 2.099-2.288 eV. Also, the linear attenuation coefficient values of gamma-rays for shielding the Cs-137 radioactive source increased at 50 °C. The transmission factor, mean free path, and half-value layer are reduced at a higher attenuation coefficient of PbO grown at 50 °C. This study evaluates the relationship between synthesized lead-oxide NSs and the radiation energy attenuation of gamma-rays. This study provided a suitable, novel, and flexible protective shield of clothes or an apron made of lead or lead oxide to protect against ionizing radiation that meets safety rules and protects medical workers from ionizing radiation.

Influence of Sm/Bi substitution on synthesis, structural, and photon interaction properties of TeO [sbnd] MoO3[sbnd] BaO [sbnd] Sm2O3[sbnd] Bi2O3 glass system

In this this paper, five transparent and non-toxic glasses with the chemical identity: 75TeO 10MoO3 10BaO (5-x)Sm2O3xBi2O3 with x = 0 (TMBS-0Bi), 2 (TMBS-2Bi), 4 (TMBS-4Bi), 4.5 (TMBS-4.5Bi), and 5 (TMBS-5Bi) were synthesized using analytic grade chemicals following the melt and quench process. The glasses were characterized for their physical, optical, structural and gamma radiation attenuation attributes. The glasses appear transparent with colour gradient dictated by chemical content. XRD data and analysis confirm the glassy nature of the prepared glasses. As the Bi2O3 content increased, the glass density increased from 5.46 to 5.64 g/cm3. The direct optical bandgap also showed variations with TMBS-5Bi having the highest value of 2.56 eV. The mass attenuation coefficient (µ/ρ) of the glasses was determined through FLUKA simulation and direct XCOM calculations. Results showed great agreement between µ/ρ obtained from both methods. The analysis of photon response parameters of the glasses indicated energy and chemical content variations for photon energies 15–15000 KeV. Generally, parameters relating to gamma ray absorption show improvement as Bi2O3 was enhanced in the glasses. therefore, TMBS-5Bi and TMBS-0Bi is the best and weakest photon absorber among the prepared glasses. The TMBS-5Bi offer good alternative as a transparent and environmentally friendly glass for radiation control applications. The TMBS-XBi glasses are attractive optical materials on one hand, they are also considered candidates in radiation protection functions.