Neutron Removal Cross Sections Research Articles

Behavior of silver tellurite glasses against gamma rays, neutrons, and ions using theoretical and the PHITS Monte Carlo method

Abstract Present work analyze the ionizing radiations attenuation behaviour, photon trajectories and dose rate reduction properties of silver tellurite glasses to investigate their potential application in radiation shielding. The shielding capability of five glass systems with different elemental compositions have been calculated with the help of theoretical software: Phy-X/PSD and NIST XCOM. For the photon energy range of 1.00 keV to 100.00 GeV, various shielding parameters are calculated, including attenuation coefficients ($MAC$, $LAC$), mean free path, half value layer, tenth value layer, effective atomic number, effective electron density, energy build up factors, energy absorption buildup factors, and fast neutron removal cross section. While the energy stopping potentials, projected range of ions (H$^{+}$, He$^{+}$, and C$^{+}$) has been presented with the help of SRIM software. Additionally photon trajectories and dose rate attenuating behavior of 10$^5$ photons generated from $^{137}$Cs and $^{60}$Co sources with activity 200.00 GBq has been studied with the help of particle and heavy ion transport (PHITS) code. It is observed that at both low and high energy levels, the glass composition, labelled S$_4$, (70TeO$_{2}$-25Ag$_2$O-2Nb$_{2}$O$_5$-2BaO-1PbO), exhibits comparable attenuation coefficients to previously recommended glass samples for radiation shielding applications. In addition to S$_4$, nine different types of glass samples and polymers with comparable densities to our glass sample, along with water, were included for comparison. The findings indicate that among all the samples tested, S$_4$ demonstrates the highest and comparable radiation-protective performance, positioning it favourably for such applications.

Radiation shielding competence of SeTeSnIn chalcogenide glassy system: Resistance against gamma irradiation

Abstract This paper reports the study of the high-energy radiation shielding characteristics of the STS glassy system. Further, the work investigates the effect of indium concentration on the high energy radiation shielding characteristics of the STS glassy system. For this purpose, a glassy Se78-xTe20Sn2Inx (x = 0, 2, 4, and 6) system was synthesized using a renowned melt quench technique whose density was measured through the Archimedes method. We have utilized an online platform, i.e., Phy-X/PSD software, to measure the different radiation shielding parameters of the SeTeSnIn glassy system. Several shielding parameters such as linear and mass attenuation coefficient, half value layer (HVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Neff), effective conductivity (Ceff), equivalent atomic number (Zeq), energy absorption build-up factor (EABF), exposure build-up factor EBF), and fast neutron removal cross-section (FNRCS) have been measured in the energy range of 15 keV to 15 MeV.

The dielectric and radiation shielding features of Zn0.9Ni0.1Co2-xFexO4 nanopowder

Nano Zn0.9Ni0.1Co2-xFexO4 (x = 0, 0.05, 0.1, 0.15) specimens were synthesized utilizing the hydrothermal method. An extensive assessment was conducted on the structure and dielectric characteristics of the fabricated specimens. The synchrotron x-ray diffraction and scanning electron microscopy techniques were employed to analyze the formed phases and the morphological characteristics of the specimens. Rietveld refinement was utilized for determining the structural and microstructural parameters of all specimens. The impact of temperature and frequency on the dielectric properties of the material is thoroughly investigated. Except for the specimen with x = 0.15, all samples exhibit ferroelectric characteristics. The electric modulus corroborated the existence of the non-Debye relaxation phenomenon and the presence of relaxation times distributed at a specific frequency. Each specimen demonstrates a singular relaxation time, which was modified by the introduction of Fe ions. Through the utilization of the Phy-X/PSD software, the radiation shielding parameters for the examined specimens were computed across a wide energy spectrum ranging from 15 KeV to 15 MeV. These parameters encompass the linear attenuation coefficients (LAC), mean free path (MFP), mass attenuation coefficient (MAC), half value length (HVL), effective nuclear number (Z eff), and fast neutron removal cross-section (FNRCS). The specimens of Zn0.9Ni0.1Co2-xFexO4 exhibit elevated FNRCS values compared to RS-253-G18, RS-360, and RS-520 commercial shielding glasses.

Zircoborate glass-ceramic composite reinforced with aluminum oxynitride: Microstructural evolution, physical properties, and charged radiation attenuation analysis

This study used the powder metallurgy method to create aluminum oxynitride (AlON)-reinforced zircoborate glass-ceramic composites. The solid-phase reaction method was used to synthesize AlON powder, which was then added to Zr-based glass-ceramic in different amounts (0, 4, and 8 % by weight) to make it stronger and harder. The prepared materials were characterized for their structural, physical, and radiation shielding properties. The density of GZr8 (AlON-free) had a value of 2.9 g/cm3, and the sintered glass-ceramic density with 4 % wt. AlON reinforcement (GZr8Al4) reached 3.05 g/cm3. The highest density of 3.11 g/cm3 was obtained for the GZr8Al8 sample with 8 % AlON wt. The Vickers hardness for GZr8, GZr8Al4, and GZr8Al8 was measured to be 4.89, 5.94, and 6.33 GPa, respectively. The AlON-reinforced GZr8 samples had fast neutron (FN) removal cross-sections of 0.0796 cm−1 and 0.0824 cm−1 for AlON content of 4 and 8 wt%, respectively. Generally, the coherent scattering cross-section (σcoh), incoherent scattering cross-section (σinc), and absorption cross-section (σabs) of thermal neutrons (TNs) increase from 0.047856 cm−1, 0.02072 cm−1, and 0.01498 cm−1, respectively for GZr8 to 0.53124 cm−1, 0.02074 cm−1, and 0.01795 cm−1, for GZr8Al8. AlON was proven to improve the ability of the Zr-based glass-ceramics to attenuate FNs and TNs. Stopping powers of electrons, protons, alpha particles and carbon ions increase with the AlON content of the materials. Comparatively, the range of charged radiation in AlON-rich samples is lower. The inclusion of AlON in the matrix of the Zr-based glass-ceramics makes it more efficient at absorbing charged radiation and can be used in ion beam or hadron therapy, ion beam analysis, or other charged radiation environments as an absorber.

Impact of natural aggregates and some industrial wastes on radiation shielding properties of heavyweight concrete: Experimental and theoretical study

The methodology to produce five concrete specimens with high density has been conducted, incorporating natural aggregates such as sand and basalt as well as commercial aggregates like lead and copper. These specimens have been designed for use in structural and radiological shielding purposes. The five specimens exhibit exceptional mechanical features, characterized by superior performance and remarkable stability. The specimen labeled heavyweight concrete with 36% Pb (HWC36Pb) has been found to have a compressive strength of 28 MPa and a tensile strength of 2.76 MPa. Furthermore, the current work specimens show excellent potential for attenuating gamma, neutron, proton, and alpha radiation, particularly at low energies. This supports their potential use in medical and nuclear facilities. Radiation attenuation results show that the specimen with the ID HWC36Pb exhibits the maximum attenuation coefficient for gamma and neutron radiation among the other investigated specimens, which were either doped with a small quantity of lead or doped with copper. The mass attenuation coefficient of HWC36Pb at a gamma energy of 662 keV was determined to be 0.0905 cm2/g. Furthermore, it demonstrates the highest fast neutron removal cross-section, measuring 0.0944 cm−1.

Tailoring the Structure, Optical and Shielding Characteristics of ZnMn2O4 Nanostructures through Sn-Doping

The current study aims to tailor the structure, optical and shielding characteristics of ZnMn2O4 nanostructures through Sn-doping. ZnMn2−xSnxO4 nanostructures were synthesized by the sol-gel technique. The sample containing 5% Sn exhibits the highest level of absorbance. ZnMn2−xSnxO4 system exhibits a maximum optical energy gap value of 2.55 eV when doped with 10% Sn, and a minimum optical energy gap value of 2.23 eV when doped with 5% Sn. The refractive index values of the samples containing 5 and 10% Sn are the highest in comparison to the other samples. The values of the non-linear optical parameters became maximum as x = 0.05. The radiation shielding constants were computed by Phy-X/PSD software. The half value length and tenth value length values reduced as ZnMn2O4 doped with Sn, implying that doped samples have better shielding capabilities than undoped ZnMn2O4. When compared to doped samples, ZnMn2O4 has the highest fast neutron removal cross-section value. ZnMn2-xSnxO4 samples demonstrate a greater rate of absorption for photons with lower energy as opposed to those with higher energy.

A comparative investigation on mechanical, gamma-ray and neutron shielding properties of some iron and boron containing concretes samples for nuclear safety applications

This study explores the gamma-ray and neutron shielding properties of fourteen different concrete samples, each tailored with varying percentages of Boron Carbide, Iron, and Iron Boride. Using the MCNP 6.3 Monte Carlo code, we calculated transmission factors for photon energies of 0.662 MeV, 1.1732 MeV, and 1.3325 MeV, and analyzed the impact of concrete thickness on shielding efficacy. Additionally, the Phy-X/PSD software was used to compute critical parameters such as linear and mass attenuation coefficients, half-value layer, tenth-value layer, mean free path, and fast neutron removal cross-section to gain a comprehensive understanding of each material's shielding capabilities. Our findings indicate that adding iron to the concrete matrix significantly enhances its attenuation properties, with the 20%Fe+80%Concrete sample outperforming all others. This composition demonstrated the lowest transmission factors across all tested energies and thicknesses, indicating superior photon attenuation. Moreover, the 20%Fe+80% Concrete exhibited the highest fast neutron removal cross-section, making it highly effective for environments requiring neutron shielding. In addition to the shielding properties, we analyzed the Elastic (Young's) Modulus of the concrete samples to understand their mechanical properties. Standard Concrete had an Elastic Modulus of 261.24 GPa, while the introduction of boron carbide significantly enhanced the Elastic Modulus, with pure boron carbide concrete exhibiting a value of 518.88 GPa. Concrete samples with varying percentages of boron carbide (5%, 10%, 15%, and 20%) showed a progressive increase in Elastic Modulus, indicating that higher proportions of boron carbide consistently enhance the material's stiffness. Conversely, concrete samples with iron boride and iron showed slight reductions in Elastic Modulus. It can be concluded that the boron carbide enhances stiffness, iron and iron boride provide a balance between stiffness and other properties. In conclusion, the 20%Fe+80%Concrete is a standout material that could greatly improve radiation shielding, offering major benefits.

Assessing the efficacy of some heavy-metal infused concrete mixtures in gamma-ray and neutron shielding applications

This study examines the radiation shielding properties of sixteen diverse concrete types encompassing both gamma-ray and neutron radiation. Concrete, a widely used material due to its low cost, high density, and efficient shielding capabilities, is investigated to determine how its varying compositions impact its ability to attenuate ionizing radiation. Utilizing the Phy-X/PSD software, the research analyses key parameters like mass attenuation coefficients, linear attenuation coefficients, and half-value layers, among others, to assess each concrete type's shielding efficiency. The findings reveal that concretes containing heavy metals such as iron and barium exhibit enhanced performance in absorbing photons, thus providing superior protection against radiation. Iron-Portland concrete demonstrated a high density of 5.80 g/cm³ and exhibited a mass attenuation coefficient (MAC) of 35.14 cm2/g at 0.1 MeV, significantly higher than MAC of ordinary concrete (i.e., 17.24 cm2/g). Significantly, Iron-Portland and Barite Concrete are highlighted for their exceptional shielding abilities, with Iron-Portland showing a fast neutron removal cross-section (ΣR) of 14.29 cm−1, compared to 11.11 cm−1 for ordinary concrete. It can be concluded that the high elemental mass fraction of iron (88.12 wt%) in Iron-Portland concrete, along with its significant density of 5.80 g/cm3, makes it the most advantageous for gamma-ray and neutron shielding applications due to its superior absorption and attenuation capabilities.

Production and characterization of ionizing radiation shielding material from algal biomass

This study employs several approaches to enhance environmental sustainability: First, algal biomass (with 52.5% protein content) was converted into value-added products. Second, residual algal biomass from protein extraction and pigment extraction and raw algal biomass were used to manufacture bioplastics. Third, radiation shielding performance of bioplastics has been investigated. As an alternative to plastics originated from petroleum-based raw materials, environmentally friendly bioplastics were derived from residual algae biomass after extraction. The gamma-ray radiation shielding properties of the produced bioplastic have been investigated using WinXCOM theoretical calculation and GEANT4 Monte Carlo (MC) simulation. Fast neutron shielding performance of the considered materials also evaluated with help of theoretical calculation and the same MC simulation. The produced bioplastics are similar to ones with commercially available PLA polymer. Sample 1 was found to be better gamma-ray attenuator while Sample 2 has the highest value of the effective neutron removal cross section. Additionally, the boron addition has resulted in lower water absorption capacity in the prepared samples. Using algae to produce more than one product as a raw material source will be an effective step toward sustainable life, and they could be an alternative gamma-ray shielding material to existing commercial polymers.

Influence of praseodymium oxide on the structural, mechanical and photon, charged particles, and neutron shielding properties of alumina borate glass

The structural, mechanical and radiation shielding properties of (69-x)B2O3-20TeO2-10Al2O3-1HfO2-xPr6O11 (where x = 0, 0.25, 0.5, 0.75, 1 mol %) glass system were investigated. This study introduces a novel approach by incorporating Pr6O11 into glass composition, highlighting its unique contributions to enhancing elastic properties, fracture toughness, hardness, and radiation shielding abilities. Experimental measurements were conducted within the energy range of 59.54–661.62 keV and theoretical calculations are made for MAC values. The presence of Pr6O11 was noted to positively influence the gamma shielding capabilities. At 59.54 keV, the addition of 0.25 mol% Pr6O11 increased the mass attenuation coefficient of the glass by 2.9 %, and the addition of 1 mol% Pr6O11 increased it by 29.8 %. The addition of 0.25 mol% Pr6O11 increased the fast neutron removal cross section of the glass by 4.4 %. Also, it is observed that the glass with 1 mol% Pr6O11 is the best shielding material against alpha and proton particles. A significant enhancement of 24.36 % in the fracture toughness value was observed, increasing from 1.059 to 1.317 MPa m1/2 at 1 mol% Pr6O11. Experimental hardness values increased from 3.374 to 3.985 GPa, resulting in an improvement of 18.11 % at 1 mol% Pr6O11. The thermal stability (ΔT, °C) value demonstrated a notable increase from 85 to 106, indicating a significant 24.7 % improvement at 0.25 mol% Pr6O11.

Radiation shielding properties of composites of TiZrNbHfTa refractory high entropy alloy reinforced with TiZrNbHfTaOx high-entropy oxide

Radiation shielding materials play a critical role in advancing the next generation of nuclear reactors. Among these, high-entropy materials with refractory properties emerge as a new category for radiation shielding applications. This study introduces TiZrNbHfTa-TiZrNbHfTaOx composites tailored for such purposes. Initially, a TiZrNbHfTa refractory high-entropy alloy (RHEA) is synthesized via mechanical alloying, followed by the oxidation of the alloy to obtain its refractory high-entropy oxide (RHEO), TiZrNbHfTaOx. Composites are then prepared by blending 5%, 10%, and 20% weight fractions of RHEO with RHEA using mechanical alloying. Comparative analysis of shielding properties reveals a decrease in mass attenuation coefficient and effective atomic number with increasing RHEO content. While RHEA exhibits superior shielding performance against gamma photons and neutrons, the composite containing 20% RHEO emerges as the optimal shield against alpha and proton irradiations. The equivalent neutron dose rate and removal cross-section values are obtained 49.8% and 0.142 for the composite with 20% RHEO, respectively. These findings, supported by computational simulations in this study, contribute valuable insights for the advancement of novel shielding materials crucial for future nuclear reactor technologies.

X-ray photoelectron spectroscopy, structural, and radiation shielding properties for transparent borosilicate glasses

The current work investigates the impact of SrO content on the structural, physical, and shielding properties of xSrO-10TiO2–10SiO2-(65-x) B2O3, where (15 ≤ x ≤ 30) glasses. X-ray diffraction (XRD), X-ray photoelectron spectroscopy (XPS), Fourier transform infrared (FTIR), and radiation shielding features were utilized to investigate the samples’ features. XRD results affirmed the amorphous behavior. The FTIR values presented many peaks attributed to SiO2 and B2O3. The Sr30B50 sample (3.048 g/cm3) showed the highest density, followed by Sr25B55 (2.936 g/cm3), Sr20B60 (2.720 g/cm3) and Sr15B65 (2.679 g/cm3). The XPS analysis of Ti 2p core level spectra reveals that Ti ions exist in both Ti4+ and Ti3+ oxidation states, with the content of Ti4+ increasing with the SrO ratio in the glass sample. The XPS analysis of O 1s core level spectra revealed that the number of non-bridging oxygen atoms is enhanced with an increase in SrO content, indicating the weakening of the glass structure. Furthermore, neutron and photon shielding properties were calculated theoretically using Phy-X software. The gamma shielding properties were enhanced with increasing SrO, while the neutron attenuation was equivalent to water. For example, the fast neutron removal cross-section (FNRCS) values are 0.101, 0.098, 0.102, and 0.101 cm−1 for Sr15B65, Sr20B60, Sr25B55, and Sr30B50, respectively. The findings suggest that the SrO improved radiation shielding properties while decreasing glass stability.

Characterization and radiation shielding efficiency of MWCNT/shape memory ternary blend composite films

In this study, the structural, X-ray and gamma-ray, and neutron shielding properties of shape memory ternary blend/multi-walled carbon nanotube (MWCNT) composite films were investigated. The composition of the composite films was defined as (100-x) poly (ε-caprolactone) (PCL):polyethylene glycol (PEG):polyvinyl chloride (PVC) + xMWCNT, where x = 0, 1, 3, 5% (mole percentage). The ternary blend/MWCNT composite films were characterized using Attenuated Total Reflectance Infrared Spectroscopy (ATR-IR), Thermogravimetric Analysis (TGA), Differential Scanning Calorimetry (DSC), X-ray Diffraction (XRD), and Scanning Electron Microscopy (SEM). Thermal results showed that the degradation temperatures of composite materials with two degradation curves increased with increasing MWCNT percentage. The appearance of the MWCNT signal along with the characteristic polymer signals in the XRD pattern may be evidence that MWCNT is homogeneously distributed in the polymer blend. The mass attenuation coefficients (MAC), half-value layer (HVL), mean free path (MFP), and effective atomic numbers (Z_eff) of the composite films were experimentally measured over an energy range of 8.04–383.85 keV. Additionally, the equivalent dose rates for fast neutrons were measured, and the exposure buildup factor (EBF) and fast neutron removal cross-section (Σ_R) were theoretically calculated. The proton and alpha shielding parameters of the ternary blend/MWCNT composite films were determined, revealing that the inclusion of higher amounts of MWCNTs in the composite structure significantly improved capability of the films in shielding against radiation and neutrons.

A comprehensive study of the shielding ability from ionizing radiation of different mortars using iron filings and bismuth oxide

The current work discusses the radiation attenuation capability and different shielding characteristics of different mortar samples. The samples were prepared by replacing different percentages of fine aggregate with iron filling and replacing different percentages of hydrated lime with Bi2O3 (0–50 wt.%). The prepared mortar samples are coded as CHBFX where X = 0, 10, 30, and 50 wt.%. The mass and linear attenuation coefficient was determined experimentally using a narrow beam technique, where a high purity germanium detector, and different point gamma-ray sources (such as Am-241, Cs-137, and Co-60). The linear attenuation coefficient was also calculated using the Monte-Carlo simulation code and the online Phy-X/PSD software. The comparison of the three methods showed a good agreement in the results. The linear attenuation coefficient drops from 19.821 to 0.053 cm−1 for CHBF0, from 27.496 to 0.057 cm−1 for CHBF10, from 42.351 to 0.064 cm−1 for CHBF30, and from 55.068 to 0.071 cm−1 for CHBF50 at photon energy range from 0.015 to 15 MeV. The half-value layer thickness, tenth-value layer thickness, and mean free path of the prepared mortar composites were also calculated photon energy ranged from 0.015 to 15 MeV. The fast neutron removal cross-section of the prepared CHBFX mortar samples have values of 0.096 cm−1, 0.098 cm−1, 0.103 cm−1, and 0.107 cm−1 for the mortar samples CHBF0, CHBF10, CHBF30, and CHBF50, respectively. The results showed that the mortar sample with the highest iron filing concentration, CHBF50, provides the best protection against gamma rays and fast neutrons which could be used in the nuclear and medical fields.

Influence of titanium dioxide doping on the attenuation and optical characteristics of magnesium borate glass systems

This research examines the effects of varying titanium oxide (TiO2) concentrations in glass formulations, denoted as [(53-x)B2O3–7MgO–20BaF2–20Na2O-xTiO2] or BMBNTix, where x varies from 0 to 8 mol% in 2 % increments, on optical properties and radiation shielding effectiveness. Using MCNP5 (MC) Monte Carlo simulations and Phy-X software, this study assesses a range of photon energies from 0.015 to 15 MeV, focusing on key radiation shielding metrics such as the linear attenuation coefficient (μ), the half-value layer (HVL), and the tenth value layer (TVL). The results reveal a clear relationship between increased TiO2 levels in the BMBNTix glasses and improved radiation shielding performance. Notably, the linear attenuation coefficient (μ) steadily climbs from BMBNTi0 to BMBNTi8, highlighting the beneficial effect of a TiO2 addition to the material's ability to attenuate radiation. This trend is inversely mirrored in HVL values, which decrease from 0.010 cm for BMBNTi0 to 7.646 cm for BMBNTi8, reflecting enhanced shielding efficiency over the entire studied photon energy range. The effective atomic number (Zeff) also showcases a dynamic range from 40.793 to 15.101, suggesting a complex relationship between TiO2 content and photon interaction. Moreover, the study indicates a slight but consistent increase in the fast neutron removal cross-section (ΣR) from 0.104 cm−1 for BMBNTi0 to 0.106 cm−1 for BMBNTi8, pointing to improved neutron shielding with greater Ti and oxygen content in the glass. These insights highlight the potential of TiO2-enriched magnesium borate glasses as superior options for effective photon and neutron shielding, particularly in nuclear medicine, emphasizing their role in enhancing radiation safety measures.

Radiation Shielding Performances and Spectroscopic Features of Replacement Materials Based on Reusing of Agricultural and Industrial Wastes

Environmental pollution increases due to the large amounts of waste production and raw material consumption depending on the increasing population. Agricultural and industrial wastes which are some of the sources of the pollution need to be reuse to reduce the negative impact on the environment and also con-tribute positive effect to the economy. In this context, industrial wastes such as clay types (red and green) and agricultural wastes such as egg shell, walnut shell and banana shell were used to prepare materials which can be used as replacement materials for construction industry. Radiation attenuation parameters (mass attenuation coefficients, effective atomic number, linear attenuation coefficients, mean free path, half-value layer, exposure and energy absorption build up factors, fast neutron removal cross-section) were acquired by Phy-X/PSD code. Spectroscopic techniques (XRD, EPR, SEM-EDS) were performed for the structural analysis. The existence of calcite main phase peaks as well as SiO2 and cellulose phases were observed by XRD. Mn+2 sextet lines with five weak doublets attributed to the forbidden transition lines of Mn+2 and a singlet with a g value of ≈2.00 were recorded by EPR. All samples examined with good protection performances can be used as substitute materials instead of cement or aggregate for the aim of reusing the wastes and supporting the environmental and economic benefits.

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.

Gamma-ray, fast neutron and charged particle shielding performance of 15Li2O-25BaO-(40-x)B2O3-20P2O5-xDy2O3 glass system

Gamma-ray, fast neutron and charged particle shielding characteristics of Dy3＋ activated glasses with composition 15Li2O-25BaO-(40-x)B2O3-20P2O5-xDy2O3 (x = 0, 0.2, 0.4, 0.6, 0.8, and 1.0 mol%) are analyzed in a wide incident energy for the first time. For gamma-ray shielding analysis, mass attenuation coefficient (MAC), mass energy absorption coefficient (μen), linear attenuation coefficient (LAC), mean free path (MFP), half-value layer (HVL), atomic cross-section (ACS), electronic cross-section (ECS), effective atomic number (Zeff), equivalent atomic number (Zeq), effective conductivity (Ceff), effective electron density (Neff), buildup factors (EABF and EBF), and kinetic energy released per unit mass of the absorbing material (KERMA) are calculated by using Phy-X/PSD and PAGEX softwares. For fast neutrons, fast neutron removal cross-section (FNRCS) is computed for all glass samples. For charged particle shielding analysis, mass stopping power (MSP), projected range (Rp), radiation yield (Ry), Zeff and Neff are computed using SRIM, ESTAR and PAGEX softwares. It is found that the glasses with increasing Dy3＋ have higher shielding potential. This suggests that the LBPDy1.0 sample has a potential use as shielding material for various applied fields.

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.

Radiation shielding effectiveness, structural, and mechanical properties of HDPE/B4C composites reinforced with Fe2O3-Al2O3-Al-Fe fillers

The fast neutron and gamma-ray attenuation properties of pure high-density polyethylene and its composites were investigated, including 90 HDPE/10 B4C (wt%) and 60 HDPE/10 B4C/30X (wt%) (Where X represents iron oxide, aluminum oxide, iron, and aluminum). The examined samples were analyzed using a scanning electron microscope, and their mechanical properties were assessed. The composite of 60 HDPE/10 B4C/30 α-Fe2O3 (wt%) shows better mechanical properties than those of other composites under investigation. 239Pu–Be was used as a source of fast neutrons with a neutron yield of 1.7 × 106 n s−1 and was detected by the Stilbene scintillator. Neutron removal cross-section with dependent parameters, the mean free path and half-value layer of the prepared composites, were calculated. Furthermore, the gamma-ray transmission through the produced composites has been examined. The composite containing 30% iron oxide exhibited superior shielding characteristics for neutrons and gamma rays compared to the other analyzed samples. The computed values of the shielding characteristics indicate that the produced composites are highly effective for shielding fast neutrons and gamma rays in radiation facilities.