Nuclear Radiation Shielding Properties Research Articles

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.

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.

Fabrication and structural, physical, and nuclear radiation shielding properties for Oxide Dispersion-Strengthened (ODS) alloys through Erbium (III) oxide, Samarium (III) oxide, and Praseodymium (III) oxide into 316L matrix

We report a comprehensive investigation on customization process of Oxide Dispersion-Strengthened alloys through Sm2O3, Pr2O3, and Er2O3 incorporation into 316L stainless steel matrix in terms of a desired enhancement in structural, physical, and nuclear radiation shielding properties. Oxide powders are incorporated into 316L stainless steel powder all with the same purity of 99.5%. These were Erbium oxide (Er2O3), Praseodymium oxide (Pr2O3), and Samarium oxide (Sm2O3). First, X-Ray diffraction and Scanning Electron Microscope/Energy-dispersive X-ray spectroscopy analyses are conducted in order to investigate their physical and structural properties. Next, two different experimental setups are employed using a133Ba and 241Am/Be sources for the measurements of gamma-ray and neutron transmission properties of Oxide Dispersion-Strengthened alloys. The maximum density increment is achieved through Er2O3 compared to other reinforced oxides. The detector counting value reached its minimum level when a 5% Er2O3 oxide dispersion was introduced into the 316L SS matrix. Similarly, the most significant degree of photon absorption, the highest values of mass attenuation coefficient, lowest half value layer, and most effective atomic number, were all attained by the same sample. Based on the findings derived from the investigation, it can be concluded that incorporating Er2O3 oxide into 316L steel can be considered as a viable option in terms of enhancing the critical properties of Oxide Dispersion-Strengthened alloys for extreme conditions such as nuclear reactors and other similar fields, where the behavioral attributes of the utilized materials are at utmost importance.

Developing of Lead/Polyurethane Micro/Nano Composite for Nuclear Shielding Novel Supplies: γ-Spectroscopy and FLUKA Simulation Techniques.

In this work, the effect of adding Pb nano/microparticles in polyurethane foams to improve thermo-physical and mechanical properties were investigated. Moreover, an attempt has been made to modify the micron-sized lead metal powder into nanostructured Pb powder using a high-energy ball mill. Two types of fillers were used, the first is Pb in micro scale and the second is Pb in nano scale. A lead/polyurethane nanocomposite is made using the in-situ polymerization process. The different characterization techniques describe the state of the dispersion of fillers in foam. The effects of these additions in the foam were evaluated, Fourier transform infrared spectroscopy (FTIR), scanning electron microscopy (SEM), transmission electron microscopy (TEM), and X-ray diffraction (XRD) have all been used to analyze the morphology and dispersion of lead in polyurethane. The findings demonstrate that lead is uniformly distributed throughout the polyurethane matrix. The compression test demonstrates that the inclusion of lead weakens the compression strength of the nanocomposites in comparison to that of pure polyurethane. The TGA study shows that the enhanced thermal stability is a result of the inclusion of fillers, especially nanofillers. The shielding efficiency has been studied, MAC, LAC, HVL, MFP and Zeff were determined either experimentally or by Monte Carlo calculations. The nuclear radiation shielding properties were simulated by the FLUKA code for the photon energy range of 0.0001-100 MeV.

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.

CoCrFeNiSi high entropy alloy: Synthesis, structural and radiation shielding properties

High entropy alloys (HEAs) have emerged as a distinct class of alloys with unique design strategies, different from traditional alloys. These alloys hold great promise for diverse applications, and the investigation of their nuclear radiation shielding properties has become an important and emerging area of research. In this experimental study, an equimolar CoCrFeNiSi HEA was prepared using the ball milling method. The focus was on characterizing the crystalline structure, morphological features, and radiation shielding properties of the synthesized HEA. X-ray diffraction analysis revealed that the HEA exhibited a face-centered cubic (FCC) phase structure. The crystallite size was significantly reduced from 23.63 nm to 3.22 nm, indicating the refinement of the microstructure. The homogeneity of the alloy was confirmed through scanning electron microscopy with energy-dispersive X-ray spectroscopy (SEM-EDX), which showed that the five elements were uniformly distributed within the powder alloy. To evaluate the radiation shielding properties, linear attenuation coefficients (LAC) of the CoCrFeNiSi HEA powder were measured using a 662 keV gamma source and a NaI(Tl) detector system (ORTEC® 905–4). The experimental LAC values were determined to be 0.2140 ± 0.01 cm⁻1. Theoretical calculations using MCNP6.2 and XCOM code were also performed and showed good agreement with the experimental results. Comparing the CoCrFeNiSi HEA with common shield materials such as thin films, glass systems, and some composites, it was found that the HEA outperformed them in terms of radiation shielding effectiveness. This demonstrates the potential of the CoCrFeNiSi HEA as an advanced alternative to conventional shielding materials, with potential applications in various fields.

Enhancement of nuclear radiation shielding properties of silicone rubber with γ‐ray irradiation induced graphene oxide modified carbonyl iron powder hybrid fillers

AbstractIn this study the graphene oxide modified carbonyl iron (GO‐CI) was prepared by γ‐ray irradiation, which was added to silicone rubber composites to enhance the nuclear radiation shielding performances. X‐ray diffraction (XRD) characterization result showed the structure and morphology of the obtained GO‐CI nanocomposites. The mixture of GO/CI and the hybrid GO‐CI were individually incorporated into the vinyl‐terminated polydimethylsiloxane (Vi‐PDMS) to prepare referenced SR/GO/CI and SR/GO‐CI composites. Compared with SR/GO/CI, the SR/GO‐CI exhibited better thermal conduction and mechanical recovery properties. Moreover, the γ‐ray radiation shielding ability of SR/GO‐CI is much higher than that of pristine SR/GO/CI. CI particles are coated by GO nanosheets to increase surface area to prevent sedimentation of CI. It implies that SR‐GO/CI composite would have potential application as the radiation hardening material with thermal conductive and nuclear radiation shielding function.

Impact of BaTiO3 on the structural, optical, and nuclear radiation shielding parameters of poly(methyl methacrylate) nanocomposites as transparent shielding material

Six weight percentages (0, 2, 5, 10, 15, and 20 wt(%)) of barium titanate BaTiO3 were doped as a nanoparticle in poly(methyl methacrylate) PMMA and their optical and nuclear radiation shielding properties were investigated. The XRD patterns, FTIR spectra and SEM images confirmed that the nanocomposite films were successfully prepared. The pure PMMA sample demonstrated a significant degree of transparency, approximately 90%. The inclusion of BaTiO3 resulted in a significant reduction in the optical bandgap while maintaining a moderate transmittance level of approximately 40% at a concentration of 10 wt (%). The direct and indirect band gap energy of PMMA were decreased from 4.81 eV to 4.62 eV–1.64 eV and 1.09 eV, respectively, after doping with 20 wt(%) BaTiO3 nanoparticles. The refractive index of the investigated samples was determined using various approaches and seen to increase after nanofiller addition. Seven energy lines, from Eu-152, Cs-137, Na-22 and Ra-226 radioactive gamma ray sources, were used to deduce the gamma ray shielding parameters of the prepared samples. Also, three neutron energy ranges were used to measure the macroscopic cross-sections for the investigated samples. The results showed good agreement between measured values of mass attenuation coefficients and those calculated by WinXCOM computer program. Furthermore, the optimal weight percentage of BaTiO3 in PMMA for attenuation of all examined gamma ray energies was 10 wt (%), whereas it was 15 wt (%) for the investigated three neutron energy ranges. In other words, a novel flexible, transparent and non-toxic polymer nanocomposite shielding material is presented and the samples containing 10–15 wt(%), demonstrates improved radiation attenuation.

Study nuclear radiation shielding, mechanical and Acoustical properties of TeO2-Na2O-BaO-TiO2 alloyed glasses

In this paper radiation shielding characteristics of tellurium glasses materials for radiation protection have been studied. The effect of different TiO2 contents in 75TeO2-Na2O-(20-x) BaO-xTiO2 (x = 0, 5, 10 and 15) glass samples are investigated on the shielding behavior, acoustic and physical parameters. However, some structural properties such as Molar Volume, Oxygen Molar Volume and Oxygen Packing Density are studied by using the Phy-X/PSD program and Monte Carlo simulations (with GEANT4 and MCNPX2.6.0 codes) in the photon energies of 0.284, 0.347, 0.511, 0.662, 0.826, and 1.173 MeV. The total trends of calculated LAC values in all four alloy glasses show that they are inversely proportional to the photon energy. It shows the abnormal behavior of Linear Attenuation Coefficient value at one point in low energies (sudden leapfrog peak between 0.3 MeV and 0.4 MeV) are shown by derived results by PhyX/PSD and GEANT4, which can be described by tellurium k-edge (in about 0.032 MeV). Finally, it can be informed that by increasing photon energy TNB-Ti15 sample has the best quality in radiation properties and a good choice for radiation protecting in various purposes such as medicine fields.

Synergic effect of some waste pozzolans on the mechanical and shielding properties of geopolymer concretes

This work aimed to investigate the effect of raw materials to geopolymer concrete; such as silica fume, metakaolin, ground granulated blast-furnace slag, and quartz powder on mechanical (compressive strength, flexural strength), physical, transport, and nuclear radiation shielding properties. The silica fume, metakaolin, ground granulated blast-furnace slag, and quartz powder used singly and/ or in combination for geopolymer mixture along with sodium-based solutions. Four different geopolymer mixtures were prepared and cured at three different temperatures (30°C, 60°C and 90°C) for three curing periods (5, 7 and 9 h). Then, the mineralogical and morphological properties were considered with X-ray diffraction (XRD), Fourier transform infrared (FTIR) and scanning electron microscopy (SEM) tests. Based on the findings, the use of metakaolin in the geopolymer mixture increased both the compressive and flexural strengths. In addition, the compressive strength of 137.5 MPa was reached in the mixture using metakaolin at 90°C and in a short period of curing, like 9 h. The metakaolin (MK) is decreased the sorptivity coefficient of the geopolymer concrete samples. Withal, extensive experimental measurements were performed to investigate the gamma-ray and fast neutron shielding properties of fabricated concretes. The mass attenuation coefficient enjoyed values such as 0.2078, 0.2078, 0.2079 and 0.2081 cm2/g for M1, M2, M3 and M4 geopolymer concretes, respectively. It was reported that the geopolymer concretes attenuated the fast neutron flux with the energy of about 4.5 MeV by 35%. All inspected geopolymer concretes exhibited excellent neutron attenuation properties, as their values ΣR greater than those of commonly used ones as the neutron absorbers.

Structural and photon/neutron attenuation features of PbNi/CNT nanocomposites: An experimental approach

In this work, PbNi/CNT nanocomposites were prepared by sodium borohydride method at varying metallic molar ratios for determination of their structural and nuclear radiation shielding properties. As-prepared PbNi/CNTs were characterized by using transmission electron microscopy (TEM), scanning electron microscopy energy-dispersive X-ray spectroscopy (SEM-EDX), elemental mapping, and X-ray diffraction (XRD). Average particle sizes of Pb40Ni60/CNT, Pb60Ni40/CNT, Pb80Ni20/CNT, and Pb20Ni80/CNT materials were obtained as 5.6, 3.8, 4.2, and 4.2 nm, respectively. Radiation attenuation properties of the produced nanocomposites were investigated experimentally by irradiating the samples with gamma photons in the 34–383 keV energy range. The accuracy of the experimental results was checked with outcomes calculated with EpiXS software. Mass attenuation coefficient (MAC) was found in the range of 22.924–0.108 cm2/g, 5.473–0.129 cm2/g, 3.767–0.109 cm2/g, and 4.626–0.128 cm2/g for Pb20Ni80/CNT, Pb80Ni20/CNT, Pb40Ni60/CNT, and Pb60Ni40/CNT samples, respectively. Also, other photon shielding parameters (HVL, Zeff, EABF, and EBF) were calculated to make a comprehensive evaluation. The results show that 30% by weight Pb80Ni20 doped CNT has the lowest HVL and buildup factors values and the largest MAC, Zeff values. Finally, macroscopic cross-section values (ΣR) were obtained to estimate the ability of the nanocomposite samples to reduce the energy of fast neutrons. It was revealed that the ΣR values of the samples were in the range of 0.158–0.169 cm−1 and they had higher ΣR values than conventional neutron moderators.

Bismuth(III) oxide and boron(III) oxide substitution in bismuth-boro-zinc glasses: A focusing in nuclear radiation shielding properties

Doping the glass structure with Bi2O3 `is known to increase structural stability, and to drastically alter physical parameters including density and molar volume. The goal of this work was to assess the nuclear radiation attenuation competences of several types of glasses based on the xBi2O3-(70-x)B2O3-8BaO-16ZnO-5.5SiO2- 0.5Sb2O3 system. In order to determine the requisite gamma shielding parameters, as well as effective conductivity at 300 K and buildup factors, five different glasses with varied Bi2O3 concentration (i.e., from 10 mol.% to 30 mol.%) were examined thoroughly. These critical parameters were determined using the Phy-X/PSD program. In addition, factors such as half value layer (HVL), tenth value layer (TVL), and mean free path (mfp) were examined over a wide energy range of 0.015–15 MeV. The findings revealed that the amount of Bi2O3 reinforced in each sample is critical in determining the samples' shielding abilities. The linear attenuation coefficients (µ) and mass attenuation coefficient (µm) values were reported in the highest level for the sample with the highest Bi2O3 content. For glass sample A5, the lowest mean free path, half value layer, and tenth value layer values were also reported. The effective conductivity and effective atomic number had an inverse relationship with photon energy, meaning that as energy increased, the effective conductivity and effective atomic number declined fast, especially in low-energy regions. The greatest values for both parameters were found in glass sample A5. Furthermore, the exposure buildup factor and energy absorption buildup factor values for glass sample A5 were the lowest. A5 glass sample with the chemical composition 30Bi2O3-(70−30) B2O3-8BaO-16ZnO-5.5SiO2- 0.5Sb2O3 and a density of 5.8391 g/cm3 was found to have exceptional gamma-ray attenuation qualities, according to our findings. It can be concluded that the prospective attributes of Bi2O3-doped glass systems and associated glass compositions would be beneficial for scientific community in terms of providing a clearer view for some advanced applications of these glass types.

Four-phases characterization of synthesised CeO2 thin films: Effect of molarity on structural, optical, physical properties and gamma-ray attenuation parameters

A group of novel CeO 2 thin films were synthesised using ultrasonic spray pyrolysis process. The composition ratios of these films were modified to investigate changes in their optical, surface, electrical, and structural characteristics. Absorbance spectra in the range 300–900 nm was acquired. Transmittance in the visible area was determined to be 50%. The optical band gap was reported to vary between 3.38 and 3.52eV using absorbance spectra. X-ray diffraction was used to analyse the films' structure, while atomic force microscopy was used to determine the surface roughness values. Spectroscopic ellipsometry and the Cauchy–Urbach model were used to calculate the thicknesses. Electrical resistivity values were determined using a four-probe system. CeO 2 thin film X-ray diffraction patterns validated the polycrystalline cubic fluorite structure. According to the data, the deposited films expand preferentially in the (2 0 0) direction. The films were found to have a high resistivity of 10 6 Ω cm. We also evaluated the nuclear radiation shielding properties of CeO 2 thin films in the 0.015–15 MeV photon energy range. The results indicated that CeO 2 thin film exhibits promising half value layers of 0.00169 cm, 0.14055 cm, 1.62665 cm, and 2.30273 cm, respectively, for 0.015 MeV, 0.15 MeV, 1 MeV, and 15 MeV CeO 2 films have been determined to be worth working on and may be promising materials for optoelectronic and nuclear security applications.

Structural, thermal and nuclear shielding properties of lithium lead phosphate glasses: Influence of lithium oxide additive

In this paper, the structural, thermal and nuclear radiation shielding properties of a new Lead–Lithium-Phosphate glass system with different amount lithium oxide were studied. The glass samples were prepared by the conventional melt-quenching method and they having compositions (75-x) P2O5– 25PbO- xLi2O with x = 0, 5, 10, 15, 20 mol%. The influence of Li2O content on the structural, thermal, radiation shielding properties, and other related properties of the synthesized glasses was studied. The structural properties were investigated using XRD and Raman spectroscopy. The glass transition temperature Tg and crystallization onset temperature Tx are estimated from the DSC profile.The GEANT4 Monte Carlo simulation code was used to estimate thermal neutron attenuation coefficient (μnt) in a wide neutron energy range of 0.0253–100 eV and ParShield code was used to calculate effective fast neutrons removal cross-section (∑R). The gamma-ray attenuation parameters such as mass attenuation coefficients (μm), effective atomic number (Zeff), effective electron density (Neff) and half-value layer (HVL) have been computed by using ParShield code in the energy range of 0.103–1.33 MeV. However, the total mass stopping power (MSP) and projected range (PR) values have been estimated for alpha particles (4He2+) and Triton particle (3H) by using SRIM in the energy range of 0.1–10 MeV.

Novel Strategy for Hazardous Cement Bypass Dust Removal: Structural, Optical and Nuclear Radiation Shielding Properties of CBD-Bismuth Borate Glass

Herein, this study introduced a novel strategy for hazardous cement bypass dust (CBD) removal via incorporated it into glassy system having the chemical formula 10Li2O–10Bi2O3–(80 − x)B2O3–xCBD, where x = 0, 10, 20 and 30%. The doped glass samples with the CBD were used as a radiation shielding material. The structural, optical and nuclear radiation shielding properties of CBD-lithium bismuth borate (LBB) glass were investigated. The optical energy gap increases from 2.22 eV for LBB + 0% CBD glass sample to 2.66 eV for LBB + 30% CBD glass sample. Also, a comparative study between the experimental data and theoretical interpretation for the attenuation coefficients was addressed via the Phy-X software database. The outcomes unveiled that the shielding parameters such as the linear attenuation coefficient, mass attenuation coefficient, and the effective atomic number were enhanced as CBD content increases. In the same time, the half-value layer, the tenth value layer, and the mean free path are reduced with the enrichment in the CBD content. Furthermore, the exposure build-up factor is inversely related to equivalent atomic numbers. Based on these findings, it was determined that the manufactured bismuth lithium-borate glass system doped cement bypass dust can be used for radiation shielding purposes.

Newly synthesized NiCoFeCrW High-Entropy Alloys (HEAs): Multiple impacts of B4C additive on structural, mechanical, and nuclear shielding properties

High-Entropy Alloys (HEAs) are regarded as potential structural materials for fusion and next-generation fission reactors, which will be required to fulfil growing nuclear energy demands. In this study, a HEA-composite was synthesized by adding B4C to an HEA containing Ni. The microstructure of the obtained HEA-composite was examined and the changes in its mechanical properties were revealed. Additionally, the nuclear radiation shielding properties of the Ni-containing HEA, and the HEA-composite are investigated using experimental and theoretical methods. Our initial findings showed that with the addition of 2.5% B4C to the alloy, the hardness increased more than two times. The addition of B4C to the HEA matrix resulted in a more than 90% and a nearly twofold increase in compressive strength. The shielding qualities of gamma-ray and neutron radiation were investigated using experimental and theoretical approaches. Our findings demonstrated that increasing the B4C reinforcement considerably enhanced the composite material's neutron attenuation capabilities. On the other hand, no significant change in the gamma-ray shielding characteristics of HEA and HEA-composite samples was observed. The gamma-ray shielding characteristics of HEA and HEA-composite samples were compared to those of other alloy shields and commercial products. Our findings indicate that both HEA and HEA-composite samples exhibit superior gamma-ray shielding characteristics when compared to the control samples. It can be concluded that increasing B4C reinforcement may be a multifunctional tool in terms of improving the mechanical properties as well as neutron attenuation properties for advanced applications in nuclear radiation facilities and next-generation fission reactors. Additionally, due to their promising material features and higher gamma-ray shielding capabilities compared to other kinds of alloys and commercial shields, HEAs may be beneficial materials.

Impact of molybdenum on optical, structure properties and gamma radiation shielding parameters of bor-ophosphate glass: Intensive experiment investigations

A group of borophosphate glasses with a nominal composition of 6ZnO–28Na2O-42-B2O3-(24-x)P2O5-xMoO3 (where; x = 0, 3, 5, and 8 wt %) were prepared by the traditional melting method. A detailed characterization of structural, optical, and nuclear radiation shielding properties was performed using experimental and in-silico methods. The amorphous structures of the synthesized glasses were observed by XRD results. Consequently, none of the samples exhibited a distinct peak. Moreover, the optical constants such as optical band gap, phonon energy, and tails of localized states of the present gasses were determined in terms of optical properties. The results showed that rigid P2O5 and MoO3 substitution did not result in a significant loss of physical and optical characteristics, and on the contrary, it resulted in enhancements in several of the key attributes on gamma-ray attenuation competencies. Our findings showed that MoO3 is a monotonic tool for borophosphate glasses in terms of changing the fundamental properties. It can be concluded that MoO3 directly affects the attenuation characteristics of gamma-ray radiation when tested. It was apparent that the MoO3 strengthening had a significant effect on radiation attenuation properties, as the ZNBPMo8 with the highest MoO3 content has attenuated the majority of incident gamma-rays.

Gamma, neutron, and heavy charged ion shielding properties of Er3+-doped and Sm3+-doped zinc borate glasses

AbstractThis study aimed to investigate the nuclear radiation shielding properties of erbium (Er)-reinforced and samarium (Sm)-reinforced borate glasses. In the 0.015–15 MeV photon energy range, attenuation coefficients, as well as half-value layer tenth-value layers, and the mean-free path have been calculated. Additionally, effective, and equivalent atomic numbers, effective atomic weight, electron density, and exposure and energy absorption build-up factors were also calculated. To evaluate the overall nuclear radiation attenuation competencies of Er-rich and Sm-rich glasses, effective removal cross-section values for fast neutrons and projected range/mass stopping power values for alpha and proton particles were also determined. The glass sample BZBEr2.0 had the highest linear and mass attenuation coefficients (µandµm), effective conductivity (Ceff), the effective number of electrons (Neff), and effective atomic number (Zeff) values as well as the lowest half-value layer (T1/2), tenth value layers (T1/10), mean free path (λ), exposure build-up factor, and energy absorption build-up factor values.µmvalues were reported as 2.337, 2.556, 2.770, 2.976, 2.108, 2.266, 2.421, 2.569, and 2.714 for BZBEr0.5, BZBEr1.0, BZBEr1.5, BZBEr2.0, BZBSm0.0, BZBSm0.5, BZBSm1.0, BZBSm1.5, and BZBSm2.0 glass samples at 0.06 MeV, respectively. The results showed that Er has a greater effect than Sm regarding the gamma-ray shielding properties of borate glasses. The results of this investigation could be used in further investigations and added to older investigations with the same aim, to aid the scientific community in determining the most appropriate rare-earth additive, to provide adequate shielding properties based on the requirement.

Synthesis and characterization of vanadium(V) oxide reinforced calcium-borate glasses: Experimental assessments on Al2O3/BaO2/ZnO contributions

This study aimed to synthesize and characterize novel calcium borate glasses based on nominal compositions of 55B2O3-35CaO-(10–x)Al2O3-xV2O5, 55B2O3-35CaO-(10–x)BaO2-xV2O5 and 55B2O3-35CaO-(10–x)ZnO-xV2O5 (where x; 0.5 and 1 mole%). Experimental methods were used to determine the optical, structural, physical, and nuclear radiation shielding properties. Density values of the synthesized glasses were measured between 2.5681 g/cm3 and 3.0231 g/cm3. All glasses exhibit a transmittance characteristic start in the visible region. The transmittance starts at approximately 370 nm and this value shifts up to 420 nm. Moreover, neutron and gamma-ray shielding properties of all glasses were measured using experimental methods. Our findings showed that ZnO and V2O5 substitution was more effective than other substitution types (i.e., Al2O3/V2O5, BaO2/V2O5) in terms of optical band gap values. Our findings also showed that BCBV0.5 sample with the highest optical band gap has superior neutron and gamma-ray shielding properties. It can be concluded that substituting ZnO and V2O5 is a more effective method of increasing the crucial neutron and gamma-ray shielding characteristics of calcium borate glasses.

The effect of rare earth on the radiation shielding properties of transparent lead-free Alumino-borophosphate glass system

The nuclear radiation shielding properties for Alumino-borophosphate (ABP) glass system with different rare earth dopants were studied. The mass attenuation coefficient (μ/ρ) values of different glass were calculated by Phy-X software for the photon energies in the energy range from 1 keV to 100 GeV. The Gamma-ray attenuation parameters such as effective atomic numbers (Zeff), half value layer (HVL), mean free path (MFP), mass attenuation coefficients (MAC) and tenth value layer (TVL) was determined by μ/ρ values. Exposure build up factors (EBF) and energy absorption build up factors (EABF) are determined by using the G-P fitting method in relation to penetration depth and the incident photon energy. In addition, the neutron radiation shielding parameters was computed and compared with conventional neutron shielding materials. The outcomes from the present investigation explore the advantages of the ABP glasses in different shielding applications.