Radiation Shielding Properties Research Articles

Impacts of siltstone rocks on the ordinary concrete's physical, mechanical and gamma-ray shielding properties: An experimental examination

A series of ordinary concrete is casted in order to examine the influence of the manganiferous siltstone rocks on the physical, mechanical, and gamma-ray shielding properties. Thus, a partial replacement for the coarse aggregates by siltstone rocks was performed during the fabrication of the currently ordinary concrete. The test revealed that raising the siltstone concentration improved the mechanical characteristics and density of the developed concretes. The addition of siltstone rocks at concentrations ranging from 0 to 40 wt% of the coarse aggregate concentration raises the density of the concrete from 2.05 g/cm3 to 2.3 g/cm3. Furthermore, partial substitution of basalt with siltstone rocks improves gamma-ray shielding properties. The experimental results for the linear attenuation coefficient show an increase in its value from 0.146 cm1 to 0.160 cm−1 when the siltstone concentration is increased between 0 and 40 wt% at 0.662 MeV. Furthermore, increasing the concentrations of siltstone affected the half-value thickness, which varied between 4.759 and 4.319 cm at 0.662 MeV. Therefore, the replacement presents a new alternative coarse aggregate that can enhance the mechanical and radiation shielding properties of ordinary concretes.

Radiation Shielding Properties of Aluminosilicate Glass Systems using Phy-X Software

In this work, we studied the radiation shielding properties of aluminosilicate glasses with constant SiO2 content. By applying Phy-X software, we calculated different radiation attenuation factors for the chosen glasses. The linear attenuation coefficient (LAC) for the chosen CaO–Al2O3–SiO2 glass systems showed an exponential decrease as the energy changes from 0.015 to 15 MeV. For the glass with composition of 35CaO-5Al2O3-60SiO2, the LAC decreases from 29.80 to 1.279 cm-1 between 0.015 and 0.05 MeV. The LAC decreases with the increase in the Al2O3 content. The minimum LAC is found for the glass with the composition of 20CaO-20Al2O3-60SiO2. The effective atomic number (Zeff) was reported, and we found that the highest Zeff is occurred at 0.015 MeV and varied between 14.55 and 16.09. The Zeff decreases when we replaced the CaO by Al2O3. The half value layer was reported and we discussed the impact of the density of the glasses on the HVL values. In the low energy range, the HVL values are small and the different compositions have close HVL. For E>0.08 MeV, the HVL is higher than 1 cm for all glasses, while for E> 0.2 MeV, the HVL becomes higher than 2 cm for all glasses. The glass with composition of 35CaO-5Al2O3-60SiO2 has better attenuation performance than the other glasses in this study.

Investigation of the Structural, Elastic, and Radiation Shielding Properties of the SiO2 –Pb3O4–ZnO –Y2O3 Glass System

Investigation of the Structural, Elastic, and Radiation Shielding Properties of the SiO2 –Pb3O4–ZnO –Y2O3 Glass System

Attenuation properties of poly methyl methacrylate reinforced with micro/nano ZrO2 as gamma-ray shields

This research aimed to examine the radiation shielding properties of unique polymer composites for medical and non-medical applications. For this purpose, polymer composites, based on poly methyl methacrylate (PMMA) as a matrix, were prepared and reinforced with micro- and nanoparticles of ZrO2 fillers at a loading of 15%, 30%, and 45% by weight. Using the high purity germanium (HPGe) detector, the suggested polymer composites’ shielding characteristics were assessed for various radioactive sources. The experimental values of the mass attenuation coefficients (MAC) of the produced composites agreed closely with those obtained theoretically from the XCOM database. Different shielding parameters were estimated at a broad range of photon energies, including the linear attenuation coefficient (μ), tenth value layer (TVL), half value layer (HVL), mean free path (MFP), effective electron density (Neff), effective atomic number (Zeff), and equivalent atomic number (Zeq), as well as exposure buildup factor (EBF) and energy absorption buildup factor (EABF) to provide more shielding information about the penetration of γ-rays into the chosen composites. The results showed that increasing the content of micro and nano ZrO2 particles in the PMMA matrix increases μ values and decreases HVL, TVL, and MFP values. P-45nZ sample with 45 wt% of ZrO2 nanoparticles had the highest μ values, which varied between 2.6546 and 0.0991 cm−1 as γ-ray photon energy increased from 0.0595 to 1.408 MeV, respectively. Furthermore, the highest relative increase rate in μ values between nano and micro composites was 17.84%, achieved for the P-45nZ sample at 59.53 keV. These findings demonstrated that ZrO2 nanoparticles shield radiation more effectively than micro ZrO2 even at the same photon energy and filler wt%. Thus, the proposed nano ZrO2/PMMA composites can be used as effective shielding materials to lessen the transmitted radiation dose in radiation facilities.

Advanced hydrostable, recyclable and degradable cellulose hybrid films as renewable alternatives to synthetic plastics

Strong, tough and sustainable materials are in high demand in various engineering applications. We demonstrate a potential sustainable hybrid film made from natural cellulose and a biobased slurry. Through a simple and scalable approach, cellulose can be processed into an advanced material with over 2.8 and 9.2-fold increase in dry strength and toughness after curing and a 728-fold increase in wet strength, respectively. In addition, these hybrid composite films display an outstanding antioxidant activity surpassing 90 %, along with excellent ultraviolet radiation shielding and thermal insulation properties. Further, the hybrid films can be fabricated by integrating all-natural materials and still guarantee their unique functionality. We also demonstrate the feasibility of a circular bioeconomy by recycling the hybrid film using a green, deep eutectic solvent to fabricate a recycled hybrid film that displays excellent mechanical and optical properties. When recycling is unsuitable or economical, the hybrid film can naturally degrade in the soil under 6 months. These encouraging findings suggest the promise of cellulose hybrid films as a renewable, low-cost, tough, and strong material with the potential to replace nonrenewable synthetic plastics and products.

Optimization radiation shielding properties of aluminum-based spinel minerals through the crystal tetrahedral and octahedral voids and their ions composition

In this research paper, we delve into the influence of crystal structure, void volumes and their ionic composition along with the atomic packing factor on the radiation attenuation properties of Al-based spinel compounds. The study investigates various Al-spinel chemical compositions explores their applications in radiation shielding. Analyzing mass attenuation coefficient (MAC) of six spinel minerals across different energy regions, we observe specific trends in scattering processes with the following sequential order: MACPleonaste > MACGahnite > MACHercynite > MACGalaxite > MACCeylonite > MACSpinel. The results demonstrated that the MAC values were influenced by the spinel chemical composition, crystal structure, and atomic arrangement in the lattice. Furthermore, the correlation between MAC values and the tetrahedral volume (Vtet), octahedral volume (Vocta), and the ratio of void volumes to the unit cell volume (R) was examined. Optimal void volumes and divalent and trivalent ion compositions were determined for different spinel minerals, leading to enhanced radiation shielding efficiency. The findings offer valuable perspectives for refining and optimization of spinel materials for use in radiation applications.

Improvement of nuclear photon and neutron shielding performance of Tm2O3 and Dy2O3 doped ceramics: An experimental study

In this study, 60KAlSi3O8+10Al2Si2O5(OH)4+(30-x)SiO2+xA2O3 (x = 0, 10, 20, 30 wt% and A = Tm, Dy) ceramics were produced by conventional method to determine their usability as shielding material against ionized gamma radiation. To investigate the ionized photon shielding properties of the fabricated materials, the photon intensities (I and I0) were experimentally measured at 81, 160, 223, 302, 356, and 383 keV energies emitted from 133Barium radioisotope, and then the mass attenuation coefficient (μρ), The linear attenuation coefficients (μ, cm−1), half-value thickness (Δ0.5), mean free path (λ), effective atomic numbers (Zeff) and electron densities (Nel) were derived experimentally. The obtained results were benchmarked with the calculated values from the EpiXS program. Also equivalent absorbed dose (EAD) values for fast neutrons were measured using BF3 gas proportional neutron detector from the Canberra NP-100B series and a241Am/Be neutron source with a 10 mCi activity. In addition, fast neutron shielding parameters (ΣR) of ceramics were also computed theoretically. The density of the fabricated ceramics varied from 2.607 g/cm3 to 4.392 g/cm3 when the Tm2O3 was raised from 0 wt% to 30 wt%. Likewise, with the addition of Dy2O3 compound, the densities of ceramics varied between 2.607 g/cm3 to 4.152 g/cm3. It was found that nuclear radiation shielding properties evolved by adding Tm2O3 and Dy2O3 compounds in the present ceramic.

Eco-friendly repurposing of by-pass waste for optics and radiation protection: addressing hazardous material challenges

This study delves into the investigation of optical and gamma radiation shielding properties of glasses formulated with varying concentrations of By-pass combined with Na2O, Fe2O3, Bi2O3, and P2O5.

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.

Investigation of the radiation shielding properties for ZnO and NiO and their based composites

Investigation of the radiation shielding properties for ZnO and NiO and their based composites

A Comprehensive Study of the Effect of BaO Doping on the Physical, Mechanical, Optical, and Radiation Shielding Properties of Borate-Based Glasses

A Comprehensive Study of the Effect of BaO Doping on the Physical, Mechanical, Optical, and Radiation Shielding Properties of Borate-Based Glasses

Structural, optical, and shielding properties of lead borate glasses doped with copper oxide

Lead borate glasses of the system 25PbO-(75-x) B2O3-xCuO (x = 0, 0.025, 0.05, and 0.1) in mol.% were synthesized via the traditional melt quenching method abbreviated as (BPbCu0, BPbCu1, BPbCu2, and BPbCu3) respectively. XRD diffraction confirmed the amorphous nature of the samples. According to FTIR spectroscopy, the function groups (BO3 and BO4) and the fraction of boron tetrahedral units (N4) were determined. The density, molar volume, packing density, and some other physical parameters were calculated and discussed. The density was increased by incorporating CuO as a substitution for B2O3, while the molar volume was decreased. The ion concentrations of Cu, inter-nuclear distance, field strength, and polaron radius were also computed. The optical absorption study suggested that the copper ions exist in the Cu2+ and act as a modifier by increasing the disorder in the glass network. Hence, the present glass behaves as a bandpass filter in the UV–vis. region. The radiation shielding properties of the as-prepared samples were theoretically calculated using the Phy-X program at energies ranging from 0.015 to 1.5 MeV. The linear and mass attenuation coefficients, as well as the half-value layer (HVL) and exposure buildup factor (EBF), have been evaluated. The results revealed that shielding parameters are affected by CuO concentrations and photon energy. Based on the results presented in the manuscript, the glass sample with 0.1 mol% CuO doping (BPbCu3) showed the best properties overall for optical and radiation shielding applications. Specifically, BPbCu3 had the highest density, refractive index, optical dielectric constant, and radiation shielding parameters such as linear attenuation coefficient and half value layer among the glass samples. The addition of 0.1 mol% CuO introduced Cu2+ ions which acted as network modifiers, increasing the disorder in the glass structure. This in turn enhanced the optical bandgap as well as the shielding capabilities against gamma radiation.

Morphology, structural, and radiation shielding characteristics of Bi2O3-B2O3-Cr2O3: ZrO2 glass ceramics

Six glass ceramics were prepared with composition (in mol %) 30Bi2O3-70B2O3 (pure sample) and (29-x) Bi2O3-70B2O3- 1Cr2O3: xZrO2 (where x = 0, 0.5, 1, 1.5, and 2) by process of melt-quenching, and subsequent two-step heat treatment method. We have studied the SEM, XRD, FTIR, and radiation shielding properties of the prepared samples. SEM micrographs and XRD spectra confirmed the formation of heterogeneous crystal phases in the samples during heat treatment. FTIR spectra revealed the presence of structural units: [BO3], [BO4], [BiO6], [ZrO6] and [CrO4−2] in the samples and their variation with the addition of ZrO2 content. EPDL2017 photoatomic and JENDL/PD-2016 photonuclear interaction databases revealed an increase in mass attenuation coefficients and a change in effective atomic numbers not exceeding 3% and 2% respectively. Mean free paths were calculated by highlighting a photonuclear absorption energy peak at ≈13.5 MeV due to the giant dipole resonance of bismuth nuclei. Fast neutron removal cross sections were determined using PHITS 3.31 spherical model simulations, which have demonstrated practical values between 0.0880 cm−1 to 0.0903 cm−1 and stability across compositions with relative differences not exceeding 3%.

Enhancing Gamma-Neutron Shielding Effectiveness of Polyvinylidene Fluoride for Potent Applications in Nuclear Industries: A Study on the Impact of Tungsten Carbide, Trioxide, and Disulfide Using EpiXS, Phy-X/PSD, and MCNP5 Code

Background: Radiation protection is crucial in various fields due to the harmful effects of radiation. Shielding is used to reduce radiation exposure, but gamma radiation poses challenges due to its high energy and penetration capabilities.Materials and Methods: This work investigates the radiation shielding properties of polyvinylidene fluoride (PVDF) samples containing different weight fraction of tungsten carbide (WC), tungsten trioxide (WO<sub>3</sub>), and tungsten disulfide (WS<sub>2</sub>). Parameters such as the mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), effective atomic number (Z<sub>eff</sub>), and macroscopic effective removal cross-section for fast neutrons (Σ<sub>R</sub>) were calculated using the Phy-X/PSD software. EpiXS simulations were conducted for MAC validation.Results and Discussion: Increasing the weight fraction of the additives resulted in higher MAC values, indicating improved radiation shielding. PVDF–xWC showed the highest percentage increase in MAC values. MFP results indicated that PVDF–0.20WC has the lowest values, suggesting superior shielding properties compared to PVDF–0.20WO<sub>3</sub> and PVDF–0.20WS<sub>2</sub>. PVDF–0.20WC also exhibited the highest Z<sub>eff</sub> values, while PVDF–0.20WS2 showed a slightly higher increase in Z<sub>eff</sub> at energies of 0.662 and 1.333 MeV. PVDF–0.20WC has demonstrated the highest Σ<sub>R</sub> value, indicating effective shielding against fast neutrons, while PVDF–0.20WS2 had the lowest Σ<sub>R</sub> value. The Monte Carlo N-Particle Transport version 5 (MCNP5) simulations showed that PVDF–xWC attenuates gamma radiation more than pure PVDF, significantly decreasing the dose equivalent rate.Conclusion: Overall, this research provides insights into the radiation shielding properties of PVDF mixtures, with PVDF–xWC showing the most promising results.

Energy build-up factors estimation for BaZr0.10Ti0.90O3, Ba0.90La0.10TiO3 and Ba0.90La0.10Zr0.10Ti0.90O3 ceramics in shielding applications

The search for materials that serve as good shields for radiation has become very important in light of the increasing exposure to ionizing radiation in various vital sectors. The aim is to search for novel materials with better radiation shielding properties that are stable, nontoxic, and abundant and environment friendly. The solid-state reaction approach has been used to synthesize a few ceramics, including BaZrXTi1-XO3, Ba1-XLaXTiO3 and Ba1-XLaXZrXTi1-XO3 (with x = 0.10) i.eBaZr0.10Ti0.90O3 (BZT), Ba0.90La0.10TiO3 (BLT), and Ba0.90La0.10Zr0.10Ti0.90O3 (BLZT). The density of the prepared samples varies from 6.3471 to 11.6003 g/cm3. The X-ray diffraction technique, shows strong peaks to confirm the crystalline structure of prepared ceramic samples. Using the G-P fitting approach, the advanced radiation shielding parameters (build-up factor) have been evaluated in the photon energy region of 1.5 keV–15 MeV. It is observed from the results that exposure buildup factor (EBF) and energy absorption buildup factor (EABF) are maximum for BLZT and has the minimum value for BZT in the entire photon energy regime. The results of this work should be useful in radiation shielding applications such as in industry, medicine, and nuclear engineering.

Structural, mechanical, optical, and radiation shielding properties for borotellurite glasses

In this work, six glass samples previously fabricated were used to prepare three glass systems by the melt-quench technique. X-ray diffraction and Fourier transform infrared studied the structure of refabricated glasses. At the same time, the Makishima–Mackenzie model was used to assess the elastic moduli for refabricated glasses. The optical properties of refabricated glasses were calculated based on UV–Vis absorption. The radiation shielding features were evaluated based on the Phy-X and SRIM programs. The X-ray diffraction results exhibited the amorphous behavior for all refabricated glasses, while the Fourier transform infrared revealed several bands related to TeO2 and B2O3. The band gap values for TBBBSr, TBBBZn, and TBBBCd glasses are 3.439, 3.236, and 3.195 eV, respectively. The Young modulus values are 59.368, 57.843, and 56.358 GPa for TBBBSr, TBBBZn, and TBBBCd glasses, which indicate superior the TBBBSr glass sample on other glasses in mechanical properties. The mechanical, optical, and Fourier transform infrared results showed high compatibility. In contrast, the TBBBCd glass recorded the highest density and gamma-ray shielding properties; for example, the linear attenuation coefficient values at 15 MeV are 0.222 cm−1 for TBBBCd, 0.214 cm−1 for TBBBZn, and 0.188 cm−1 for TBBBSr. While, the TBBBZn glass showed the highest neutron shielding feature; for example, the fast neutron removal cross section is 0.088, 0.091, and 0.092 cm−1 for TBBBSr, TBBBZn, and TBBBCd, respectively. On the other hand, the TBBBSr displayed the highest shielding features for charged particles. In conclusion, the TBBBSr glass can be nominated for radiation shielding applications based on its superior mechanical properties and ability to stop charged particles.

Radiation Shielding Features of Glass Fiber Reinforced Cast Polyamide Using Phy-X/PSD and SRIM Software

The utilization of various materials for their nuclear radiation shielding properties has been the subject of a growing number of research and development projects. In this study, the radiation shielding characteristics of E-glass fiber reinforced cast polyamide were evaluated. E-glass is a form of glass fiber frequently utilized as a reinforcement in various composite materials to provide more durability, stiffness, and strength. Samples S1-S7 were defined according to various compositions of E-glass fiber contents (SiO2, Al2O3, B2O3, MgO, CaO, Na2O and K2O) and cast polyamide (C12H22N2O2). Within the energy range 0.015-15 MeV, the shielding parameters: Linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half and tenth value layers (HVL, TVL), mean free path (mfp), effective atomic number (Zeff), atomic and electronic cross sections (ACS, ECS), fast neutron removal cross-section (FNRCS) and exposure buildup factor (EBF) were analyzed. E-glass fiber reinforced cast polyamide S7 (70% glass fiber content) exhibited higher values of LAC, MAC and Zeff and lower values of HVL, TVL, and mfp proving it to be a better radiation shielding material among the samples. An abrupt reduction in values of Zeff was discerned within the photoelectric absorption-dominant region, contrasted with a stable trend within the Compton scattering-dominant region, and a marginal elevation was noted in the pair production region. The maximum and minimum values of FNRCS were observed for samples S1 (10% glass fiber content) and S5 (50% glass fiber content) respectively. Hence, S1 would be the most effective material in fast neutron shielding. At 35 mfp penetration depth, the minimum EBF values belonged to S7 in lower and intermediate regions (0.015-3 MeV) whereas S1 showed the minimum values at higher energy regions (4-15 MeV). Furthermore, the mass stopping power (MSP) and projected range (PR) of the samples for alpha and proton particles were determined using SRIM-2008 codes. S7 exhibited better shielding features for alpha and proton particles with lower values of mass stopping power and projected range. The reinforcement of glass fiber in the cast polyamide has been noticed to have a significant impact on the shielding performance of polymer composites.

X-ray/gamma radiation shielding properties of zinc ferrite nanoparticles synthesised via solution combustion method.

Zinc ferrite (ZnFe2O4) nanoparticles were synthesised via solution combustion method using urea as a fuel. The synthesised samples were characterised with various techniques. The cubic structure with Fd-3m space group is confirmed by Powder X-ray Diffraction and Bragg's reflection. The crystallite size estimated from Scherrer's method was found to be 40nm. The agglomerated irregular shape and sized surface morphology was confirmed by Scanning Electron Microscopy image. The direct energy band gap determined from Wood and Tauc's relation was found to be 5.25eV. Using a NaI (Tl) detector and multi-channel analyser, the described sample was examined for X-ray and gamma ray shielding characteristics in the energy range of 0.081-1.332MeV. The measured shielding values are in good agreement with the theory, however below 356keV, there is a little variation of up to 10%. The current work offers up new possibilities for using this simple, affordable, effective and low temperature approach to create nanomaterials for X-ray and gamma ray shielding.

Sm2O3 doping-adjusted radiation shielding properties and optical stability under sunlight irradiation of B2O3–Na2O–Sm2O3–Fe2O3 glass

In this work, we prepared sodium borate glass doped with different amounts of iron oxide (Fe2O3) and samarium oxide (Sm2O3). The effects of replacing Fe2O3 with Sm2O3 on the absorbance, optical band gap, Urbach energy, and radiation shielding parameters were studied. With further additions of Sm2O3, the optical band gap values increased from 2.50 to 2.67 eV, while Urbach energy values decreased from 0.49 to 0.42 eV. Further, we explored the effect of sunlight on the absorbance, optical band gaps, and Urbach energy at 90 min of irradiation time. With further exposure to sunlight, the values of the optical band gaps decreased and Urbach energy increased as the exposure time increased from 0 to 90 min. Moreover, the percent of change in absorbance, optical band gap, Urbach energy, refractive index, nonlinear refractive index and third order susceptibility for the glass samples containing the highest concentration of Sm2O3 is insignificant (<10%). The small percentage changes in absorbance, optical band gap, and Urbach energy show that the glasses are stable when exposed to sunlight. On the other hand, the inclusion of higher concentrations of Sm2O3 leads to improved radiation shielding capabilities, as seen by the increased values of the mass attenuation coefficient and half-value layer. Herein, the investigated glasses are both more transparent and more effective at shielding radiation; they're prime candidates for use in this field.

Predicting the effective atomic number of glass systems using machine learning algorithms

This study investigates the calculation of the effective atomic number (Zeff) of glass systems through the application of machine learning algorithms. Specifically, Artificial Neural Network (ANN), Random Forest (RF), and Extreme Gradient Boosting (XGBoost) were employed and evaluated using k-fold cross-validation. The assessment of model performance was done using the coefficient of determination (R2) and root mean squared error (RMSE) as metrics. The findings reveal that among the models, the Artificial Neural Network (ANN) consistently exhibited superior predictive capabilities in estimating Zeff, with R2 of 0.99 in all testing folds. This research presents a new and potentially alternative approach for estimating effective atomic numbers of glass systems and can be expanded to assess various radiation shielding properties. Additionally, unlike conventional software, it offers distinct advantages. The application of this technique can be beneficial in the design of novel glass compositions for specific radiation shielding purposes.