Half Value Layer Research Articles

Development of heavy mineral filler based FRP composites for (low energy) radiation shielding application

The present study deals with fabricating and characterizing glass fiber reinforced epoxy composites with heavy mineral filler (magnetite particles) for potential low-energy radiation shielding applications. The composite materials were fabricated by the hand layup method. Glass/epoxy composite was used as control sample, and radiation shielding composites were manufactured by mixing 20 and 30% (by weight) magnetite particles with epoxy resin. It was revealed that the tensile properties of the magnetite-modified composites were increased, and the composites containing 30% filler exhibited maximum improvement than the control ones. Further assessment of the composite samples was performed by DMA (Dynamic Mechanical Analysis), TGA (Thermogravimetric Analysis), FTIR (Fourier-Transform Infrared) spectroscopy, water uptake (%), and SEM (Scanning Electron Microscopy) testing. The radiation shielding ability of the control and filler-modified composites was assessed by using a gamma (γ) radiation source (60Co). Then, the shielding efficiency was characterized by radiation-reduced intensity (%), LAC (Linear Attenuation Coefficient), MAC (Mass Attenuation Coefficient), HVL (Half Value Layer), TVL (Tenth Value Layer), and SVL (Sixteenth Value Layer). It was revealed that the 30% magnetite filler content composite experienced relatively good attenuation performance against γ-ray than other studied composites.

A study for gamma attenuation behavior of polyimide (PI) film by MPPC

Although lead is a very good radiation shielding material, its toxicity has led researchers to find alternative materials instead of it. Moreover, as the use of Kapton polyimide (PI) film in nuclear power plants and space exploration increases, the need to reveal the radiation degradation properties of this material has come along. In this regard, in the present study, it is aimed to determine the mass and linear attenuation coefficients, half value layer, tenth value layer, mean free path and radiation protection efficiency attenuation parameters for this material, experimentally and theoretically, by using the gammas of the 133Ba radioisotope. Experimental gamma attenuation measurements were made by a spectrometer using a Hamamatsu multi pixel photon counter device with a silicon photomultiplier sensor. The constant fraction discrimination timing method was used to reduce the electronic noise of the spectrometer. The attenuation parameters determined experimentally by following two ways were compared with the theoretical ones obtained from the XCOM program.

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.

Gamma and neutron attenuation of SiO2–B2O3–BaO–Li2O glasses doped with CeO2

Abstract The demonstrations impact of CeO2 on the radiation shielding properties of SiO2–B2O3–BaO–Li2O glasses has been investigated. The observed trend in density ρ ranged from 3.127 to 4.022 g/cm³, whereas the molar volume V m of these glasses decreased. The half-value layers (HVL), and mean free paths (MFP) of CL glasses reinforce the notion that the presence of Ce ions, particularly in CL2, enhances the ability of glasses’ to attenuate gamma rays. The effective electron density (N eff) increases with the addition of CeO2, suggesting a correlation between the enhancement of radiation shielding properties and the amount of CeO2 incorporated into the glasses.

Study of optical, structural and radiation shielding properties of (55 − x)TeO2–20ZnO–25B2O3–xEr2O3 glass matrix

Abstract Erbium doped zinc boro-tellurite (EZBT) glass samples with molar composition of (55 − x)TeO2–20ZnO–25B2O3–xEr2O3 (x = 0.0, 0.5, 1.0, 1.5 and 2.0 mol.%) were prepared by a conventional melt quenching technique. The prepared samples were characterised using X-ray diffraction, Fourier transform infrared spectroscopy and ultraviolet–visible spectroscopy techniques to investigate the structural, optical and dielectric properties. To study the radiation shielding capabilities, the parameters such as mass attenuation coefficient (μ m), half-value layer (HVL), effective atomic number (Z eff) etc., were evaluated using WinXCom software. Judd–Ofelt analysis was carried out to determine the intensity of electronic transitions and other radiative transition parameters within the 4f shell of erbium ions. The μ m values in a range of (108.5–0.03) cm2 g−1 for energy range (0.01–10) MeV were obtained for 2.0 mol.% erbium-doped tellurite glass matrix. The μ m and HVL values were also compared with conventionally used ordinary concrete and specific lead borate glass at certain energies. The detailed investigation of this current EZBT glass matrix is very useful in the specific optical and radiation shielding applications of this EZBT glass.

Radiation shielding for inertial electrostatic confinement fusion system utilizing concrete and water

In this investigation, the impact of water thickness and various types of concrete materials, each characterized by different densities and elemental compositions, is examined for their role in shielding a radiation generator based on Inertial Electrostatic Confinement Fusion (IECF) device. The study focuses on assessing several vital parameters, including the effective removal cross-section (∑Rt) for fast neutrons, total mass attenuation coefficients (μmt), linear attenuation coefficients (μl), half-value layer (HVL), and mean free path (MFP) for X-rays across different concrete types. Different water thicknesses around the IECF chamber, ranging from 0.5 to 10.0 cm, are investigated, and five concrete types are evaluated: Ilmenite-magnetite Concrete (IMC), Ordinary Concrete-1 (OC1), Barite-containing Concrete (BC), Ordinary Concrete-2 (OC2), and Serpentine-containing Concrete (SC). The results indicate that, among these materials, SC requires the least thickness to attenuate 2.45 MeV generated from IECF to 1/100th of its initial intensity across varying water thicknesses (6.5 cm in case of 5 cm water thickness). The values of μmt, HVL, and MFP are also calculated for different water thicknesses and X-ray energies (ranging from 0.2 to 3.0 MeV). These calculations highlight BC as the material requiring the least thickness to attenuate X-rays to 1/100th of their initial intensity. Moreover, neutron dose rate measurements are conducted on a commercial IECF system shielded with 50 cm of water and operated at a neutron intensity of 105 ns−1, which was ∼12 nSv/h on average, approximately 0.002% of the initial intensity. This underscores the efficacy of water shielding in attenuating the outcomes of IECF.

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).

Effect of different metal oxides on the Radiation shielding features of borate glasses

Three zinc barium-borate glasses were produced in the current work, incorporating different metal oxides (MO) (CaO, TiO2, and CuO) via the melt quenching technique under a 1100 °C melting temperature for 60 min. The fabricated samples' density is 4.112 g/cm3, 4.157 g/cm3, and 4.261 g/cm3 for glasses dopped with CaO, TiO2, and CuO, respectively. Additionally, the Makishima-Mackenzie model was employed to evaluate the effect of metal oxides on the fabricated glasses' mechanical properties. The study shows that the glasses with TiO2 have the highest mechanical moduli and microhardness which reach 4.67 GPa. The gamma-ray shielding properties in the 0.033–2.506 MeV energy interval were estimated by applying Monte Carlo simulation. The study demonstrates that the glass samples containing CuO exhibit the highest linear attenuation coefficient (LAC) when compared to the glasses containing Ca and TiO2 compounds. The LAC of the CuO-doped glasses varied between 28.367 cm−1 and 0.163 cm−1 when the photon energy was raised between 0.033 MeV and 2.506 MeV. Also, the study shows good shielding parameters (half-value layer, lead's equivalent thickness, and radiation protection efficiency) for the glasses doped CuO compared to glasses doped Ca and TiO2.

Experimental examination on physical and radiation shielding features of boro-silicate glasses doped with varying amounts of BaO

Investigations were conducted on the addition of barium's impact on the radiation shielding and physical attributes of five different glasses, designated S1–S5, with varying BaO contents. Using two point sources namely Co60 and Cs137 along with a scintillation detector [NaI(TL)], experimental measurements were made of the shielding parameters of γ-rays, namely the effective atomic number (Zeff), electron density (Nel), half-value layer (HVL), linear attenuation coefficient (μ), mass attenuation coefficient (μm), mean free path (λ), and radiation protection effectiveness at the energies of 0.664, 1.177, and 1.334 MeV, and comparisons made with recently considered glasses as well as frequently employed materials for γ-ray shielding. The results show that the examined glasses' physical and radiation shielding qualities are improved by the addition of BaO. The μ values increased from 0.245 to 0.275 cm−1 (0.662 MeV), from 0.174 to 0.198 cm−1 (1.173 MeV), and from 0.161 to 0.189 (1.332 MeV). The observed values of HVL decreased from 2.83, 3.98, and 4.3 cm to 2.5, 3.5, and 3.62 cm at 0.662, 1.173, and 1.332 MeV, respectively, for the samples S1 and S5. In addition, the S5 glass sample was determined to have the best protection against photon among all the samples that were evaluated, as well as against recently considered glasses and those materials often utilized for gamma-ray shielding purposes.

Structural, elastic, thermo-physical and gamma radiation shielding efficiency of MnO2 doped TeO2-PbO-ZnO glasses

This paper presents the fabrication of glasses with chemical formula [(TeO2)0.70 – (ZnO)0.22 – (PbO)0.08] 1-x (MnO2)x where x = 0.02, 0.04, 0.06, 0.08 and 0.1 using melt quenching technique. The main objective is to explore the structural, elastic and gamma ray shielding efficiency of the glasses. The study was conducted using density and molar volume measurements, X-ray diffraction analysis, Fourier transform infrared analysis, non-destructive ultrasonic analysis, and theoretical assessment of the glasses’ gamma ray shielding efficiency using the Phy-X/PSD software. High density values in the range of 5.611–5.735 gcm−3 and the XRD analysis showed no sharp peak indicating the amorphous nature of the glasses. The FTIR spectra revealed the presence of both TeO3 and TeO4 structural units. The values of the elastic moduli microhardness, Debye and softening temperatures, acoustic impedance, diffusion constant, Thermal expansion coefficient and latent heat of melting were studied and discussed among others. Efficiency parameters of radiation shielding such as the coefficients of mass and linear attenuation, effective atomic number, half and tenth value layers, mean free path and effective electron density were calculated theoretically and discussed. Based on the results discussed, the studied MnO2 doped TeO2-PbO-ZnO glasses appeared to be mechanically strong, and thermally stable for radiation shielding applications. Moreso, the glasses appeared to be better in terms of radiation shielding efficiency than commercial concrete materials like serpentine, barite, ferrite, and chromite.

Gamma-Ray Shielding Capacity of Bi2O3-SiO2-B2O3 Glass Powders with Different Bi2O3 Contents

In the present work, features of the ionizing radiation shielding of Bi2O3-SiO2-B2O3 glass powders with different Bi2O3 contents (45–60 mass%) has been investigated by using GAMOS (version 6.2). The validation of generated GAMOS simulation geometry has been provided by comparing the results with standard XCOM data for mass attenuation coefficients of glass powders. The Monte Carlo simulations were used to score photons that traveled in an absorber within the energy range of 0.01 MeV to 20 MeV, depending on the parameter under study. The simulation model involved a monoenergetic point source producing a pencil beam, absorber, and detector. We have calculated the mass attenuation coefficient (MAC), Half-value layer (HVL), Tenth-value layer (TVL), and Mean Free Path (MFP). The greatest linear attenuation coefficients in the whole energy range are related to Bi60 and the lowest were to Bi45. The obtained results were compared and these results are in good agreement with the obtained values from the XCOM program

Evaluation the Shielding Properties of Various Water Equivalent Materials Using Different Calculation Methods and Monte Carlo

In this study, the linear attenuation coefficients (LAC), mass attenuation coefficients (MAC), half-value layer (HVL), and mean free path (MFP) of various materials such as water equivalent, ABS, Presage, RMI457, RW3, SW557, Epoxy, A150, Rhizophora spp., and Nylon-12 have been calculated using the Monte Carlo simulation method, EpiXS, Phy-X/PSD, and XCOM. Additionally, the fast neutron effective removal cross sections (ΣR) have been calculated using the empirical calculation method, Phy-X/PSD, MRCsC program, experimental and MNCP5 with the help of fast neutron mass removal cross sections. Among all the materials studied, Nylon-12 has the highest ΣR value. The calculated values of HVL, MFP, LAC, and MAC reveal that RW3, Epoxy, and Presage are the best materials in terms of their shielding properties, respectively.

Physical and dosimetric characterisation of different Contrast-Enhanced digital mammographic systems: A multicentric study

PurposeContrast-enhanced digital mammography (CEDM) is a relatively new imaging technique recombining low- and high-energy mammograms to emphasise iodine contrast. This work aims to perform a multicentric physical and dosimetric characterisation of four state-of-the-art CEDM systems. MethodsWe evaluated tube output, half-value-layer (HVL) for low- and high-energy and average glandular dose (AGD) in a wide range of equivalent breast thicknesses. CIRS phantom 022 was used to estimate the overall performance of a CEDM examination in the subtracted image in terms of the iodine difference signal (S). To calculate dosimetric impact of CEDM examination, we collected 4542 acquisitions on patients. ResultsEven if CEDM acquisition strategies differ, all the systems presented a linear behaviour between S and iodine concentration. The curve fit slopes expressed in PV/mg/cm2 were in the range [92–97] for Fujifilm, [31–32] for GE Healthcare, [35–36] for Hologic, and [114–130] for IMS. Dosimetric data from patients were matched with AGD values calculated using equivalent PMMA thicknesses. Fujifilm exhibited the lowest values, while GE Healthcare showed the highest. ConclusionThe subtracted image showed the ability of all the systems to give important information about the linearity of the signal with the iodine concentrations. All the patient-collected doses were under the AGD EUREF 2D Acceptable limit, except for patients with thicknesses ≤35 mm belonging to GE Healthcare and Hologic, which were slightly over. This work demonstrates the importance of testing each CEDM system to know how it performs regarding dose and the relationship between PV and iodine concentration.

Study on the shielding performance of bismuth oxide as a spent fuel dry storage container based on Monte Carlo simulation

For traditional spent fuel shielding materials, due to physical and chemical defects and cost constraints, they have been unable to meet the needs. Therefore, this paper carries out the first discussion on the application and performance of bismuth in neutron shielding by establishing Monte Carlo simulation on the neutron flux model of shielded spent fuel. Firstly, functional fillers such as bismuth oxide, lead oxide, boron oxide, gadolinium oxide and tungsten oxide are added to the matrices to compare the shielding rates of aluminum alloy matrix and silicone rubber matrix. The shielding rate of silicone rubber mixture is higher than aluminum alloy mixture, reaching more than 56%. The optimal addition proportion of bismuth oxide and lead oxide is 30%, and the neutron radiation protection efficiency reaches 60%. Then, the mass attenuation coefficients of bismuth oxide, lead oxide, boron oxide, gadolinium oxide and tungsten oxide in silicone rubber matrix are simulated with the change of functional fillers proportion and neutron energy. This simulation result shows that the mixture with functional fillers has good shielding performance for low energy neutrons, but poor shielding effect for high energy neutrons. Finally, in order to further evaluate the possibility of replacing lead oxide with bismuth oxide as shielding material, the half-value layers and various properties of bismuth oxide and lead oxide are compared. The results show that the shielding properties of bismuth oxide and lead oxide are basically the same, and the mechanical properties, heat resistance, radiation resistance and environmental protection of bismuth oxide are better than that of lead oxide. Therefore, in the case of neutron source strengths in the range of 0.01–6 MeV and secondary gamma rays produced below 2.5 MeV, bismuth can replace lead in neutron shielding applications.

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.

Sm3+ doping-adjusted mechanical, dielectric, and radiation shielding properties of cobalt copper nanoferrites

The scarcity of research on the shielding properties of spinel ferrites underscores the necessity for more rigorous investigations. Consequently, this study introduces a facile synthesis method for Co, Cu, and Sm spinel nanoferrites (referred to as CCS nanoferrites) using the citrate combustion technique. The investigation focuses on their mechanical, dielectric, and gamma-ray shielding parameters. Gamma-ray shielding features are obtained theoretically via the Phy-X database. The particle size, nature, and distribution of the present CCS nanoferrites were analyzed using HR-TEM microscopy. HR-TEM results reveal both the spherical shapes and the aggregation of nanoparticles. These observations can be attributed to the interplay of high surface energy and magnetic interactions among the components of the CCS nanoferrites. The Co0.5Cu0.5Sm0.15Fe1.85O4 nanoferrite exhibits an optimal dielectric constant value of 4587, with an enhanced ratio of 1618% compared to the pristine CCS0 sample. Additionally, it demonstrates an optimal conductivity of 38.59 μ (Ω·m)−1, with an enhanced ratio of 1105%. Furthermore, the loss is reduced to 2.65, showing an improvement ratio of 54% compared to the pristine nanoferrite at room temperature and 50 Hz. Moreover, the longitudinal modulus, shear modulus, Young's modulus, and bulk modulus of the nanoferrite Co0.5Cu0.5Sm0.15Fe1.85O4 were increased from 1.79 to 4.96 GPa, 0.32–0.93 GPa, 0.88–2.56 GPa, and 1.37–3.73 GPa, respectively, when compared to the pristine sample. The comparative study of half-value layers at 0.662 MeV revealed that CCS nanoferrites exhibit smaller half-value layers than common radiation shielding materials. Additionally, the study highlighted the enhanced radiation shielding performance of the nanoferrites. Concerning the dielectric, mechanical, and ionizing radiation shielding properties of the CCS spinel nanoferrites, the CCS5 (with the highest Sm content) has the optimum ionizing radiation shielding ability with the highest dielectric and mechanical parameters compared to the other samples. The implications of these findings extend to potential applications in biomedicine, radiation protection, and the optimization of electronic devices operating in radiation fields.

Shielding parameters and optical stability of sodium alumino-borate glasses against gamma rays by iron oxide additives

The development of various industries and technologies necessitates a greater utilization of ionizing radiation, such as gamma rays. Herein, we investigate the shielding parameters and the stability of the optical parameters of sodium alumino-borate glasses against gamma rays by different iron oxide (Fe2O3) additives. We found that the Fe2O3 additives improved the shielding parameters. Moreover, the influence of various doses of γ rays (50, 100, and 150 kGy) on the optical characteristics of the performed glasses was studied. For example, the influence of gamma doses on the optical absorbance (A), optical band gap (Eg), Urbach energy (EU), refractive index (no), electronegativity (X), electron polarizability (αo), and nonlinear refractive index (n2). The optical absorbance of all glass samples increased, particularly in the visible range, with further irradiation.Furthermore, the reduced optical band gap and Urbach energy values grow as the gamma irradiation increases, which are attributed to the increased number of donor centres. Conversely, an investigation was conducted on the ability of the material to protect against radiation. We found that the Fe2O3 additives improved the shielding parameters. Furthermore, the half-value layer results of the glassy samples in question were compared to those of conventional radiation shielding materials and glasses. Therefore, the glass samples work better at blocking radiation than conventional window glass when employed for radiation shielding purposes.

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.