Fast Neutron Removal Cross Sections Research Articles

Enhancing radiation shielding effectiveness: a comparative study of barium-doped tellurite glasses for gamma and neutron radiation protection

This study investigated the radiation shielding performance of the xBaO-(30-x)TeO2-35Bi2O3-35B2O3 glass system, where x = 5, 10, 15, 20 and 25, using Phy-X/PSD software and MCNPX Monte Carlo code. Key radiation shielding indicators, including attenuation coefficients, half value layer (HVL), tenth value layer (TVL), effective atomic number (Zeff), mean free path (MFP), and build-up factors, were measured within the energy range of 0.015–15 MeV. Further, the study assessed the glasses' capacity to block fast neutrons, using the fast neutron removal cross-section (ΣR) as a metric. The results showed that gamma shielding effectiveness follows the order: BaTBiB-1 < BaTBiB-2 < BaTBiB-3 < BaTBiB-4 < BaTBiB-5 at all photon energies. Additionally, the ΣR values for BaTBiB-1 to BaTBiB-5 glasses were 0.10179, 0.10263, 0.10362, 0.10581, and 0.10623 cm−1, respectively. Therefore, the findings demonstrate that including BaO enhances the gamma and neutron shielding characteristics of tellurite glasses, making them valuable for radiation-related applications.

Physical, structural and nuclear radiation shielding behavior of Ni–Cu–Zn Fe2O4 ferrite nanoparticles

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

Evaluation of gamma and neutron radiation shielding parameters of some glass materials by Monte Carlo and theoretical method

The present study investigates the gamma-ray and neutron shielding properties of PbCu3Ti4O12, lithium borate (Li2B4O7), lithium borate glasses doped with dolomite (CaMg(CO3)) and neodymium oxide (Nd2O3) to assess their effectiveness as shielding materials against ionizing radiation. The gamma-ray shielding properties, including the attenuation and absorption characteristics of the materials were examined and compared using Geant4-based GATE simulation, XCOM, and EpiXS in the photon energy range of 80-2000 keV. When the shielding properties of the available materials were compared, it was determined that Li2B4O7-Nd2O3, PbCu3Ti4O12, Li2B4O7-CaMg(CO3), and Li2B4O7 exhibited the best shielding properties, in order from most effective to least effective. The neutron shielding properties of these materials, including scattering, absorption, and moderation capabilities, were also determined using MRCsC, Phy-X/PSD and estimation ΣR/ρ of elements. The results were then compared with the current literature. Li2B4O7, CaMg(CO3), and Nd2O3-doped lithium borate glass samples showed higher effective fast neutron removal cross-section values than water and concrete in all calculation methods. It shows that the investigated glass materials are better gamma and neutron beam absorbers and have the potential for use in gamma and neutron beam shielding applications.

Case study of Er- and Dy-doped boron-aluminosilicate glasses on radiation shielding performance in the energy range 0.015–10 MeV with MCNP6.2

The use of radiation-shielding materials has significantly increased with the advancement of new technologies. The present work aims to demonstrate that the nuclear shielding properties of boron-aluminosilicate glasses can be enhanced by doping with rare earth elements (REEs) such as erbium (Er) and dysprosium (Dy). Testing was performed by mixing different ratios of dopants into the glass system. This procedure was implemented on 13Al2O3–21B2O3-35.4SiO2-(30.6-X) Er2O3-X(Dy2O3) glass, where X = 0, 15.3, 22.1, and 30.6. MCNP6.2, SRIM, PSD, ROOT software, and XCOM databases were used as tools. MCNP6.2 software and XCOM databases were used to calculate, simulate, and validate the mass attenuation cross-sections for 15 selected gamma energies ranging from 0.01 MeV to 10 MeV. On the other hand, SRIM was used to obtain information about the mass stopping power (MSP) and stopping distance, the so-called projected range (PR), for charged particles of H+1 and He+2. Likewise, the PSD was only used to obtain a fast neutron removal cross-section (FNRCS) per density value for each element. This is referred to as the macroscopic neutron cross-section for fast neutron removal in the literature. Finally, the data analysis framework ROOT was used for calculations and graphical representations. To validate this study, the radiation-shielding properties of the material were compared with the globally accepted mass attenuation coefficient database of XCOM using MCNP6.2 simulation results. The proximity between these two is promising. The accuracy of the study was determined by examining the relative error values. The results indicate a strong correlation between the database and theoretical data. Radiation shielding properties such as mass and linear attenuation coefficients (MAC and LAC), half and tenth value layers (HVL and TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Neff), effective conductivity (Ceff), and fast neutron removal cross-sections (FNRCS) against gamma rays suggested that the lowest X ratio indicated the highest protection. However, the MSP and PR values for the charged particles at most energies indicate the lowest protection with the lowest X ratio in the glass mixture. Finally, the glass shield with the lowest X ratio provided the highest neutron protection, similar to gamma rays. In summary, dysprosium and erbium doping in boron-aluminosilicate glasses can be tailored to specify different requirements for gamma-ray and particle attenuation, as well as neutron absorption. This study aims to fill a gap in the literature by providing a basis for future research on shielding materials based on doped boron-aluminosilicate glasses using high-atomic-number particles, such as REEs, as a radiation protection medium.

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&lt;sub&gt;3&lt;/sub&gt;), and tungsten disulfide (WS&lt;sub&gt;2&lt;/sub&gt;). Parameters such as the mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), effective atomic number (Z&lt;sub&gt;eff&lt;/sub&gt;), and macroscopic effective removal cross-section for fast neutrons (Σ&lt;sub&gt;R&lt;/sub&gt;) 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&lt;sub&gt;3&lt;/sub&gt; and PVDF–0.20WS&lt;sub&gt;2&lt;/sub&gt;. PVDF–0.20WC also exhibited the highest Z&lt;sub&gt;eff&lt;/sub&gt; values, while PVDF–0.20WS2 showed a slightly higher increase in Z&lt;sub&gt;eff&lt;/sub&gt; at energies of 0.662 and 1.333 MeV. PVDF–0.20WC has demonstrated the highest Σ&lt;sub&gt;R&lt;/sub&gt; value, indicating effective shielding against fast neutrons, while PVDF–0.20WS2 had the lowest Σ&lt;sub&gt;R&lt;/sub&gt; 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.

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%.

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 Na2O–P2O5 glasses doped with MnO experimentally and using FLUKA and Phy-X

This research focused on examining the radiation shielding performance of (50% - x/2)P2O5-(50%-x/2)Na2O-xMnO (where x = 0, 5, 15, 25, and 33 mol%) glass system. The shielding review covered the radiation of photons, electrons, particles of heavy-charged, and neutrons. Hence, multiple parameters such as coefficient of mass attenuation (μm), transmission and buildup factors (HVL, MFP, EBF, and EABF), effective atomic number for samples (Zeff), and removal cross-section for fast neutron (FNRCS) of the selected samples were investigated. The results are determined experimentally and by employing FLUKA Monte Carlo software and Phy-X (ZeXTRA and PSD) theoretical programs. A relative discrepancy (RD) and a root-mean-square error (RMSE) were applied to verify the deviation between FLUKA and Phy-X values. An excellent agreement is noticed between measured, simulated, and calculated results. The research revealed that increasing MnO content improves the gamma, electron and heavy charged particle shielding efficiency of studied glasses. Although the addition of MnO has an insignificant impact on FNRCS (from 0.086 to 0.092 cm−1), obtained results identified the relationship between the packing density and shield ability against neutrons for ternary phosphate glasses. We found that the HVL values dropped from 13.898 cm to 11.568 cm at 15 MeV. A range of 7–12 for gamma, 8–12 for electron, 10–11 for proton, 10–11 for alpha, and 9–11 for carbon ion was the maximum value of Zeff that could be obtained. These glasses' shielding behaviors were contrasted with those of conventional materials. Accordingly, the sample with the highest mole fraction (x = 33 %) has higher shielding efficiency than ordinary concrete, Pyrex, and RS253-G18. Finally, the studied glass system can be a good compromise between highest effectiveness of shielding, lowest fabrication cost and environment-friendly shield.

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.

Elucidating the influences of MoO3 in Na2O- ZnO - B2O3 - SiO2: Fabrication, optical, and γ-ray protection properties for the novel high-density glasses

The melt-quenching method was employed to synthesize glasses with varying compositions within the xMoO3-(30−x) Na2O- 5ZnO - 43.5B2O3 - 21.5SiO2 system, where (0 ≤x≤ 10) mol%. The densities increased from 2.93 to 3.67 g/cm3, while their molar volumes decreased from 22.48 to 20.18 cm3/mol. Based on the measurements, the optical band gap of the base glass was 3.53 eV. At its highest MoO3 content, this value decreased to 2.34 eV. The Urbach energy values for NaMo0, NaMo2, NaMo4, NaMo6, and NaMo10 glasses were 0.258, 0.323, 0.348, 0.37, and 0.435 eV, respectively. With an increase in molybdenum level, it was observed that the refractive index values also increased. These structural, optical, and radiation shielding behaviors were attributed to the structural modifications resulting from substituting Na2O with MoO3, leading to improved radiation shielding efficiency with the addition of MoO3. The Fast Neutron Removal Cross Section (FNRCS) (∑R) for the NaMo0, NaMo2, NaMo4, NaMo6, and NaMo10 glasses were 0.116 cm−1, 0.12 cm−1, 0.127 cm−1, 0.131 cm−1, and 0.135 cm−1, respectively. From the current work, we may conclude that NaMo glasses can serve as efficient shields in nuclear radiation environments. In general, it can be deduced that adding Na2O-ZnO-B2O3-SiO2 glasses improves their optical characteristics and enhances their capacity to absorb neutrons and photons for use in nuclear medicine applications.

Shielding performance of metal oxide nanoparticles-doped polypropylene composites against gamma rays and neutrons exposure

This paper compares the theoretically measured attenuation parameters of a new type of nanocomposite shielding materials against γ-rays (energy range of 0.015 to 15 MeV) and neutrons (energy range of 0.0254 eV to 4.5 MeV) with the ones calculated using Phy-x/PSD and NGCal software. Nine nanocomposites (acted as shields) were made using hematite (Fe2O3) and cadmium oxide (CdO) nanoparticles-doped polypropylene (PP). The influence of various doping contents (x = 15, 30, 50, 75 wt%) on the shielding characteristics of the nanocomposites of composition (100-x)PP-(x)Fe2O3 and (100-x)PP-(x)CdO were examined. Radioactive isotopes like Am-241 (0.06 MeV), Ba-133 (0.081 and 0.356 MeV), Cs-137 (0.662 MeV), and Co-60 (1.173 and 1.333 MeV) were used as γ-ray sources. In addition, thermal (0.0254 eV) and fast neutrons (4 and 4.5 MeV) were used. The results revealed that the shielding performance of the proposed nanocomposites was significantly enhanced due to nanoscale metal-oxide doping. The mass attenuation coefficient (MAC) values of the PP sample impregnated with 75 wt% CdO nanoparticles varied from 0.768 cm2/g to 27.788 cm2/g and 0.018 cm2/g to 0.034 cm2/g at energies of 0.015 MeV and 15 MeV. Furthermore, it was observed that the values of fast neutron removal cross-sections (FNRCS) were impacted with an increase of 0.1162 cm-1 to 0.1225 cm-1. In addition, the linear attenuation factor (LAF) values improved intensely with increased CdO nanoparticle concentrations. The shield made using 75 wt% of CdO displayed the best shielding performance against high energy neutrons and γ irradiation.

Investigated mechanical, physical parameters and Gamma-Neutron radiation shielding of the rare earth (Er2O3/CeO2) doped barium borate glass: Role of the melting time and temperature

In this study, we aimed to explore the effects of CeO2/Er2O3, melting time, and temperature on the physical, radiation shielding, and mechanical properties of a glass composition. Specifically, we examined a glass composition comprising of 60B2O3-(40-X) BaO-XMO (where MO- Er2O3/CeO2 and X = 0.5,1.0,1.5 mol percentage). To assess the radiation shielding capabilities of the glass structure, we conducted theoretical evaluations including determining the mass Attenuation Coefficients (MAC), Fast Neutron Removal Cross-Section (FNRCS), and Mean Free Path (MFP). Furthermore, the study involved investigating the mechanical properties of borate glasses with CeO2 and Er2O3 doping, specifically examining Young's modulus, Bulk modulus, Shear modulus, and Longitudinal modulus. The obtained results were then compared. In order to determine the radiation shielding parameters, the Phy-X/PSD program and Geant4 simulation were utilized, covering an energy range from 0 to 10 MeV. The results indicate that there is strong agreement between the Phy-X/PSD and Monte Carlo simulation results for MAC values for glass samples. Our research suggests that these glasses have superior radiation shielding capabilities compared to commonly used materials for blocking radiation. This suggests that these glasses have great potential for use as effective shielding materials in radiation protection applications. It was observed that doping 1.5 mol% of Er2O3 in the lowest temperature and the longest time decreased the reflectivity of the gamma rays of the barium borate glass compared to the doping 1.5 mol% of CeO2.

Dielectric, conductivity properties, elastic moduli, and gamma-ray attenuation abilities: A wide-ranging investigation into Molybdenum added ferrite nanoparticles

The auto combustion technique was employed to synthesis magnesium nano ferrite (MgMoxFe2-xO4). The impact of Mo-doped on the crystal’s structural, morphological, and elastic properties were inspected by applying x-ray diffraction (XRD), scanning electron microscopy (SEM), transmission electron microscopy (TEM) and Fourier transform infrared (FTIR) spectroscopy techniques. Pursuant to the XRD analysis, all samples have a cubic structure with single-phase. The average crystallite size was identified to be in the nanometer range confirmed by SEM and TEM investigations. FTIR data was implemented to assign the force constants of the octahedral and tetrahedral sites. Elastic moduli including the Poisson ratio, Young’s modulus, bulk modulus, and rigidity modulus have been estimated. The division of elastic moduli for all synthesized concentrations was interpreted using binding forces between ions of the cubic lattice spinel. Over and above, the AC conductivity (σ AC) and dielectric properties and their frequency dependence were investigated for the nano ferrites samples as a function of dopant Mo content and temperature. Finally, the radiation shielding capacities of the proposed samples against gamma and fast neutron radiation have been assessed. The findings reveal that the higher the Mo content, the lower the value of the mass attenuation coefficient. There is no significant diversity between the obtained mass attenuation coefficients for the nano and the micro. Among the samples investigated in this study, the highest Mo concentration sample had the largest fast neutron removal cross-section.

Investigation of the structural, mechanical, radiation and neutron shielding properties of the TeO2-B2O3-Li2O-MoO3-CuO glass system

In this study, the structural, mechanical, radiation and neutron shielding properties of (78-x)(0.4TeO2-0.6B2O3)− 20Li2O-xMoO3-2CuO glass system, were investigated. A variety of characterisation methods, including optical absorption spectroscopy, FTIR, EPR, and X-ray diffraction, were used to examine the structural characteristics. Molecular orbital coefficients were calculated from EPR and optical absorption measurements. EPR lines of both Cu2+ and Mo5+ ions were observed in the EPR spectra. The mechanical properties were assessed through experimental measurements, while the elastic properties were evaluated using the semi-empirical approaches of the Makishima and Mackenzie model, along with the bond compression model. The inclusion of 4% MoO3 led to noteworthy enhancements in both hardness and fracture toughness. Hardness increased from 4.364 to 4.664 GPa, and fracture toughness improved from 0.980 to 1.226 MPa.m1/2. The mass attenuation coefficients (MAC), mean free paths (MFP), half-value layers (HVL), and effective atomic numbers (Zeff) were measured in the energy range of 59.54–661.62 keV. The measurement of equivalent dose rates resulting from the absorption of fast neutrons was conducted utilizing a 241Am-Be fast neutron source with an activity of 10 mCi. The exposure buildup factor (EBF) and the fast neutron removal cross section (ΣR) were therotically calculated. The potential suitability of glasses for nuclear security applications was assessed by evaluating their proton and alpha shielding properties. The study found that glasses containing higher amounts of TeO2 and MoO3, within the TeO2-B2O3-Li2O-MoO3-CuO composition, demonstrated enhanced capabilities for shielding against radiation and neutrons.

A new nanocomposite of copper oxide and magnetite intercalated into Attapulgite clay to enhance the radiation shielding

The effects of Magnetite (Fe3O4) on the radiation shielding properties of different nanocomposites from Attapulgite (ATP) intercalated with different copper oxide (CuO) and magnetite nano (Fe3O4) concentrations were investigated. Different nanocomposites from ATP intercalated with different copper oxide CuO and magnetite nano Fe3O4 concentrations have been synthesized and implemented toward radiation attenuation. The different percent were as the following 40% ATP + X Fe3O4 + (60%–X) CuO that abbreviated to [AT40FeXCu60-x] where X = 15.0%, 30.0%, 45.0%. The ATP and one of the prepared nanocomposites have been characterized using different techniques: FT-IR, TGA, XRD, EDX, and SEM. The density of the synthesized materials was determined. Then their radiation shielding properties were established using GEANT4 and Phy-X software in the selected range of photon energies of 0.015 – 15 MeV. The linear attenuation coefficient (μ), the mass attenuation coefficient (μm), the mean free path (MFP), the half value layer (T1/2), the tenth value layer (T1/10), the effective atomic number (Zeff), and the equivalent atomic number (Zeq) have been calculated to find out the radiation shielding characteristics of the new novel nanocomposites. The μm values were varied from 4.5894 to 0.0204 cm2 g-1 for Base, from 11.9780 to 0.02172 cm2 g-1 for AT40Fe15Cu45, from 12.5030 to 0.02190 cm2 g-1 for AT40Fe45Cu15 and finally from 12.2480 to 0.02181 cm2 g-1 for AT40Fe30Cu30 at photon energy range from 0.015 to 15 MeV. The results showed that the values of the radiation shielding parameters increased with increasing nano Fe3O4 concentration, and the AT40Fe45Cu15 sample has the highest μm and μ and lowest T1/2, T1/10 and MFP. The results of this study have important implications for the development of new radiation-shielding materials. ATP-doped Fe3O4-CuO glasses are a promising new class of radiation shielding materials with improved properties. In conclusion, the study found that the nanocomposite materials with higher nano Fe3O4 concentration have better shielding qualities against γ-rays and neutrons. The AT40Fe45Cu15 sample has the highest shielding qualities for γ-rays, while the AT40Fe30Cu30 sample has the highest fast neutron removal cross-section.

Gamma-ray shielding analysis on natural rubber composites fortified with barium tungstate (BaWO4)

Emission of radiation is a significant phenomenon having impacts on various fields, and its harmful effects must be minimized. To achieve this, radiation protection and dosimetry have been developed to ensure safe radiation limits. In this experimental study, we investigated the gamma-ray shielding properties of a composite material made from natural rubber with six different proportions of Barium Tungstate (ranging from 0 to 100 phr). The study revealed that the addition of Barium Tungstate (BaWO4) to natural rubber significantly improved the characteristics of gamma radiation shielding. The composite containing maximum proportion of BaWO4 (NRBW-100) exhibited the highest linear attenuation coefficient (LAC) value, measuring 0.307 cm-1 at an energy of 662 keV. At the same energy value, the LAC values were found to vary from 0.137 to 0.307 cm-1 across samples having different concentrations of BaWO4 (0 to 100 phr). To further assess the shielding properties, simulations were conducted using the Phy-X/PSD code, and the characteristic parameters such as mass attenuation coefficient (MAC), mean free path (MFP), half-value length (HVL), tenth-value length (TVL), effective atomic number (Zeff), effective electron density (Neff), effective conductivity (Ceff), and fast neutron removal cross-section (FNRCS) were theoretically evaluated. FNRC values range from 0.068 cm-1 to 0.108 cm-1 across concentrations of BaWO4 from 0 to 100 phr. Experimental measurements showed good agreement with theoretical calculations obtained from simulation results. We have also compared the shielding characteristics of these samples with that of other commonly used materials.

Synthesis and optimization of alkaline earth borate glasses doped with Fe2O3: Significance of BaO/MgO on the physical, structural features and radiation shielding performance

In this study, MgO–BaO–B2O3–Fe2O3 glasses were synthesized using the conventional melt and quench method, and the role of BaO and MgO in dictating their structural, physical, and optical properties was investigated. The fast neutrons, electrons, and heavy charged radiation transmission abilities of the glasses were delineated with the aim of evaluating their capacity to act as radiation insulators. The density of the glasses decreased from 3.40 g/cm3 to 2.89 g/cm3 as the MgO content increased. Also, the obtained optical bandgap increased from 1.90 eV to 2.20 eV with the increase of MgO in the MBBFe glasses. The stopping powers of electrons vary from 1.39 to 11.01 MeVcm2/g, 1.41–11.37 MeVcm2/g, 1.43–11.69 MeVcm2/g, 1.44–11.87 MeVcm2/g and 1.46–12.05 MeVcm2/g for glasses with MgO contents of 0 (MBBFe0), 5 (MBBFe1), 10 (MBBFe2), 12.5 (MBBFe3), and 15 (MBBFe4) mol%, respectively. Generally, the increase in the MgO content of the glasses led to increased mass stopping powers of the protons, alpha particles, and carbon ions. The replacement of BaO with MgO compromised the thermal neutron interaction probabilities of the present glassy specimens. The MBBFe-0 glass had the best thermal neutron interaction cross sections. The fast neutron removal cross-section of the glasses was within the range of 0.1037–0.1070 cm−1 with MBBFe-3 having the highest value and MBBFe-4 the least. The increase in the BaO suppresses photon buildup within the glass system. The MBBFe-glasses displayed good physical and optical properties, photon and neutron shielding abilities, which makes them attractive for diverse shielding and optical functions.

Tailoring a correlation between fracture resistance improvement, elastic moduli, mechanical and nuclear radiation shielding properties for sodium-borate glasses through Gallium(III) oxide incorporation

In the event of unanticipated events or emergency situations, such as equipment malfunctions or accidents, it is crucial for radiation shielding materials to preserve their structural integrity. Enhancing the fracture resistance of glasses has a wide range of benefits that extend to safety, durability, cost savings, energy efficiency, environmental considerations, technological innovation, consumer confidence, manufacturing efficiency, and reduced downtime. This research examines the characteristics of sodium-borate glasses with a nominal composition of 25Na2O-xGa2O3-(75-x)B2O3, (where x: 5, 10, 15, 20, 25, 27.5, and 30 mol%). The aim is to enhance fracture resistant qualities and radiation absorption with the addition of Ga2O3 into the glass composition. In addition to elastic moduli and mechanical properties, gamma-ray and fast neutron removal cross section values are determined for each glass sample. In addition to enhancing mechanical characteristics and elastic moduli, the use of Ga2O3 reinforcement has shown notable improvements in the gamma-ray and fast neutron absorption properties of sodium-borate glass samples. The NGB31.4 sample demonstrated the highest level of improvement in gamma-ray and neutron absorption characteristics. For example, the mass attenuation coefficients were calculated as 1.86645 cm2/g, 1.92189 cm2/g, 1.98875 cm2/g, 2.04052 cm2/g, 2.10506 cm2/g, 2.16271 cm2/g, and 2.17266 cm2/g for NGB5, NGB10, NGB15, NGB20, NGB25, NGB30.5, and NGB31.4 at 15 MeV photon energy, respectively. This enhancement was accomplished by incorporating Ga2O3 into the baseline sample at a mole percentage of 31.4 %. Hence, it can be concluded that the incorporation of Ga2O3 into sodium-borate glasses has the potential to serve as a systematic mechanism, leading to enhancements in mechanical strength and radiation absorption characteristics, thereby making these glasses more suitable for their intended applications. Among these samples, the greatest level of integration observed was 31.4 % mole Ga2O3. The lack of ability to examine the behavioral alterations resulting from higher Ga2O3 content in sodium-borate glasses may be regarded as a limitation of the present study. However, it is very advisable to do more research among the scientific community to thoroughly explore the potential impact of Ga2O3 on sodium-borate glasses.

Fe-nanoparticle effect on polypropylene for effective radiation protection: Simulation and theoretical study

An evaluation of the gamma-neutron shielding capabilities of polymer nanocomposite materials based on polypropylene and iron nanoparticles is presented in this study. The chemical composition of the materials is (100-x) PP-Fex, (where x = 0.1, 0.3, 0.5, 1, 2 and 5 wt percent). For the proposed polymer samples with photon energies ranging from 30 to 2000 KeV, the mass attenuation coefficient (MAC), a crucial parameter for studying gamma-ray shielding capability, was calculated using the Geant4 Monte Carlo code. Results were compared with those predicted by EpiXS. The values of the Geant4 code and the EpiXS software were both found to be in excellent agreement. Using the mass attenuation coefficient values, we determined the linear attenuation coefficients, electron density, effective atomic number, and half value layer for all the samples. The shielding properties of the polymer samples were also evaluated by estimating both the fast neutron removal cross-section and the mean free path of the fast neutron at energies between 0.25 and 5.5 keV. The study's findings indicate a positive correlation between the Fe nanoparticle content and the gamma-ray shielding performance of PP-Fe polymer samples. Out of the several glasses that were evaluated, it was found that the PP-Fe5 polymer sample demonstrates the highest efficacy in terms of gamma-ray shielding. Moreover, the polymer sample PP-Fe5, which consists of 5 mol% of iron (Fe), exhibits the highest value of ∑R (1.10650 cm-1) and the lowest value of the mean free path for fast neutrons. This indicates that the PP-Fe5 possesses better gamma-neutron shielding efficiency.

An investigation of some ionizing radiation interaction parameters in selected composite scintillation materials

In this study, the interaction parameters of neutrons, charge particles and gamma rays in seven inorganic scintillation materials with densities ranged from 3.86 to 8.30 g/cm3 were theoretically examined. SRIM Monte Carlo software was used to determine the range of H + , H e + + , A u + and O − − ions in the energy range (0.01–20) MeV, Phy-X/PSD while Py-MLBUF computer programs were used to estimate gamma radiation interaction parameters in the energy range (0.02–15) MeV. The electron total stopping power and range values at energies ranging from 0.01 to 1000 MeV were calculated using the ESTAR NIST program. The fast neutron removal cross-section (FNRCS) and the macroscopic effective removal cross-section (MRCS) were calculated using the Phy-X/PSD and MRCS tools, respectively. The outcomes of this research showed that the range of H + , H e + + , A u + and O − − ions increased with decreasing sample density but decreased with increasing projectile energies; the largest range of H + is 2090 µm in the lowest density S1 sample, while the range of A u + is 5.16 µm in the same sample. The denser sample S7 had the highest stopping power and the lowest range at higher electron energies. The S1 sample had the highest calculated HVL value of 5.403 cm, while the S7 sample had the lowest calculated HVL value of 0.0008 cm. Rising sample density causes the MAC to rise, while rising gamma energy causes the MAC to decrease. The highest MAC value recorded was 107 cm2/g at 0.015 MeV in the S7 sample, and the lowest value recorded was 0.0369 cm2/g at 15 MeV in the S1 sample. For all inorganic scintillation samples at particular gamma energies, the standard deviations for the MAC, HVL and Zeff values between the Phy-X/PSD and, Py-MLBUF programs were calculated. With energy range variation, the results for Zeff for the two samples S2 and S4 appeared to be constant. Regards to the fast neutrons, the heights value’s of FNRCS, and MRCS were recorded for S7.