Half Value Layer Research Articles

Influence of doping soda-lime-silica glasses with Gd2O3, In2O3, and La2O3 on the enhancing of their physical, opto-mechanical and radiation shielding properties

A series of soda-lime-silicate glasses doped Gd2O3, In2O3, and La2O3 rare earth ions was prepared using the melt-quenching technique. The prepared glass samples are designed depending on a chemical composition of (15-X)Na2O – 30CaO – 55SiO2 –XM2O3, where X = 1.0 mol% and M = Ga (NCSG), In (NCSI), and La (NCSL). The amorphous state of the synthesized samples confirmed by XRD analysis, and structural changes were studied via density (ρg), molar volume (Vm), Oxygen molar volume (Vo), and Oxygen packing density (OPD). The mechanical and shielding attenuation parameters of the produced glasses were also projected. The ρg of prepared glasses increased from 2.742 to 2.829 g/cm3 as a result of M2O3-dopant with high molecular weight rare earth oxides. Whereas, the physical parameters Vm, Vo, and OPD were behave in the same trend. Elastic moduli were improved when Na2O replaced with M2O3. The M2O3/Na2O replacement led to increase stiffer and rigidity of the prepared glasses. The NCSL sample was possessed the lowest optical energy band (Eopt.) values (3.45 eV and 2.63 eV for direct and indirect transitions). The NCSL glass sample possessed the highest mass (MAC) and linear (LAC) absorption capacity. In addition, the same glass sample verified the lowest values of half-value layer (HVL) and mean free path (MFP). Thus, the sample coded as NCSL sample including La2O3 is a superior for optical and radiation shielding capacities among all studied glasses. Therefore, the studied glasses can be applied for several optical and radiation shielding applications.

Investigation of the radiosensitive properties of curcumin and temozolomide

Radiotherapy, one of the cancer treatment strategies, uses ionizing radiation to destroy cancer cells. It is very important to know the photon interaction parameters of curcumin, which has both anti-cancer and cancer-protective properties, to determine the penetration and energy accumulation in the interaction of radiation with tissue. In this work, the linear attenuation coefficient (LAC, μ), mass attenuation coefficient (MAC, μ/ρ), mean free path (MFP), half value layer (HVL), effective atomic number (Zeff), and electron density (Nel) of curcumin and temozolomide have been determined experimentally at 53.16 keV, 80.99 keV, 276.39 keV, 302.85 keV, 356.61 keV and 383.84 keV photon energies emitted from Ba133 point source by using the ULEGe detector. Besides, the radiation interaction parameters were calculated theoretically using the EpiXS software program. Also, the exposure buildup factors (EBF and EABF) of these compounds were determined up to 40 mfp in the energy range 0.015–15 MeV. The experimental and theoretical mass attenuation coefficients have been found to agree. The gamma-ray absorption efficiency of curcumin is approximately 3.89% higher than that of temozolomide. Temozolomide has approximately 25.6% higher fast neutron removal cross-section than curcumin.

Radiation Shielding Analysis of Multi-Component Glasses: Effects of Varying BaO, PbO2 and Gd2O3 Concentrations

This work investigates the impact of BaO, PbO2, and Gd2O3 on newly developed borate glasses’ radiation shielding characteristics. The transmission factor (TF) of the glasses is almost zero at the low energy of 0.0395 MeV, which indicates favorable low-energy photon shielding. The maximum TF is reported at 1.46 MeV for the free Gd2O3 glass sample, ranging from 0.89 (0.5 cm thickness) to 0.73 (1.5 cm thickness). Moreover, with more BaO, PbO2, and Gd2O3 content added to the glasses, the TF decreases, indicating an enhancement in the efficiency of the glasses’ radiation protection with the introduction of BaO, PbO2, and Gd2O3. There is a 4.309 to 5.068 g cm−3 increase in the glasses’ density, and, as a result, the mean free path decreases, suggesting improved performance for radiation protection with the adding of more BaO, PbO2, and Gd2O3 contents to the glasses. At 0.122 MeV, the free Gd2O3 glass’s half value layer value is 0.098 cm, while the tenth value layer is 0.325 cm.

Gamma ray shielding ability of Y3+ doped borophosphate glasses

Abstract Four selected Y2O3 doped borophosphate glass samples are prepared using melt quench technique. The structural properties such as density and molar volume are measured. The density (ρ) increases from 3.1384 to 3.4613 g/cm3 whereas molar volume (Vm) decreases from 60.84 to 55.00 cm3 mol−1 with addition of Y2O3 cm3 mol−1 content. The lattice of the glasses has been tested via X-ray diffraction which is a good technique for confirming the structural properties of these glasses and FTIR spectra. In addition, radiation shielding parameters for glasses were performed theoretically utilizing XCOM program for various gamma ray energy and experimentally using NaI(Ti) scintillation detector, The glasses were irradiated using energies 0.664, 1.174 and 1.334 MeV emitted by Cs-137 and Co-60 radioactive point sources respectively. Shielding parameters as leaner (μ), mass attenuation coefficients (μ/ρ) and half value layer (HVL), tenth value layer (TVL) and mean free path (MFP). The concentration of Y2O3 increases the (μ/ρ) increases, the HVL, TVL, and MFP values have inverse way. Superior radiation shielding is confirmed by the glass sample containing (3%, mole) of yttrium oxide. The results show that the borophosphate glasses doped with Y2O3 can be used to shield gamma rays.

Investigation of the gamma ray shielding properties of Epoxy based on Bi2O3/GO nanocomposite

Abstract One of the important carbon materials, graphene oxide (GO), has several oxygen-containing functional groups. Due to its unique structure, it has attracted increasing interest in multidisciplinary studies of physical and chemical attributes. In this work, Bismuth Oxide nanoparticles (Bi2O3) is prepared and functionalized with graphene oxide nanosheets (Bi2O3-GO). The Bi2O3 and Bi2O3-GO nanocomposite were mixed with epoxy by changing the percentages to 1%, 2.5%, 5%, and 10%. The study used a hyper-pure germanium detector to investigate the attenuation characteristics of the prepared samples. Ba133, Cs137, and Co60 point sources were used at photon energies of 81, 276, 302, 356, and 383 keV for Ba133, 661 keV for Cs137, and 1173 and 1332 keV for Co60. The linear attenuation coefficient, mass attenuation coefficient, half-value layer, and tenth-value layer were estimated to investigate the radiation shielding characteristics of the prepared samples. The linear attenuation coefficient (μ) values varied from 0.45 to 0.88, 0.23 to 0.89, and 0.31 to 0.77 for Ba133, Cs137, and Co60, respectively. The mass attenuation coefficient (μm) values varied from 0.18 to 0.50, 0.19 to 0.50, and 0.15 to 0.50 for Ba133, Cs137, and Co60, respectively. Half-value layer (HVL) values varied from 0.79 to 1.55, 0.78 to 3.07, and 0.9 to 2.26 for Ba133, Cs137, and Co60, respectively. Tenth-value layer (TVL) values varied from 2.61 to 5.16, 2.58 to 10.19, and 2.98 to 7.51 for Ba133, Cs137, and Co60, respectively.

γ-radiation-induced centers in irradiated perovskite SrCeO3 and their role in thermally stimulated reactions: Fluorescence, thermally stimulated luminescence, electron paramagnetic resonance and shielding studies

One promising host for actinide radioactive wastes is orthorhombic perovskite-type oxide. Perovskite SrCeO3 ceramic was synthesized by nitrate-fuel combustion, which includes the organic fuel glycine. Powder X-ray diffraction was utilized to determine the structural features, and γ-radiation-induced changes and shielding properties were investigated in perovskite SrCeO3. In a mixed-phase sample, a bright sky-blue luminescence was observed, and two thermoluminescence (TL) peaks were seen in irradiated SrCeO3 ceramic. Electron paramagnetic resonance (EPR) spectrum in γ-irradiated SrCeO3 ceramic had contributions from five defect centers. Center I having an isotropic g-value equal to 2.0283, is ascribed to an O− ion, while center II with an axial g-tensor with principal values g|| = 2.0224 and g⊥ = 2.0068 is determined as an O2− ion. O− ion relates to the TL peak at 215 °C. Center III with a g-value equal to 2.0009 is identified as an F+ center and is related to the 185 °C TL peak. The defect center associated with center IV is also identified as an F+ center. An additional defect center in the higher field region of the spectrum is assigned to an F+ center, and the center results from an F-center (oxygen vacancy with two electrons). The mass attenuation coefficients, effective atomic numbers, and half-value layer thicknesses concerning shielding property effectiveness were computed and it was found that the perovskite SrCeO3 ceramic provided superior γ-shielding properties.

Investigation on radiation shielding potentials of barium calcium aluminosilicate glass material using silicon carbide nanotubes reinforcement

This work investigated the gamma ray attenuation power of barium calcium aluminosilicate glass by using silicon carbide nanotube modifiers. Shielding efficiency of BaO–15CaO–5Al2O3–10B2O3–35SiO2 was investigated by adding different concentrations of silicon carbide nanotubes (10, 15, 20, 25 mol %). Amorphous and fine characteristics of the prepared glass materials were analyzed using XRD and FTIR techniques. In the results obtained, absence of sharp peaks in the XRD pattern revealed that the prepared glass was amorphous. Analysis of the radiation shielding properties was tested against gamma radiation by using PHY-X/PSD software. Various shielding parameters such as linear attenuation coefficient, mass attenuation coefficient, half value layer, tenth value layer, mean free path, and effective atomic number were determined to access the radiation shielding strength of the prepared samples. From the obtained results, composites of barium calcium aluminosilicate and silicon carbide nanotubes (sample 1) with higher values of mass attenuation coefficient (32.92 cm2/g) and effective atomic number (52.02) provided superior gamma ray attenuation. Results also revealed that the density and chemical composition of the prepared glass samples strongly influence photon interactions and weakly influence electronic interactions during the photon attenuation process. The results demonstrated that increasing the weight fractions of silicon carbide nanotubes in the glass samples increases the shielding properties.

Scaling up features of photocatalytic degradation and radiation shielding of multicomponent Cr–Co–Zn nanoferrites

Optical, photocatalytic activity, and radiation shielding studies were conducted on CrxCo0.8Zn0.2Fe2-xO4 (0.0 ≤ x ≤ 0.1, Δx = 0.02) nanoferrites for water treatment and radiation shielding applications. The optical absorption analysis revealed that the optical band gap energy values range from 1.864 to 1.803 eV as assessed through Tauc plots. Further analysis of photocatalytic degradation showed that the Cr0.06Co0.8Zn0.2Fe1.94O4 sample exhibited superior methylene blue (MB) dye removal compared to other samples, with an efficiency of 96.74% in 60 min. Additionally, the present nanoferrites exhibited excellent stability in photocatalytic degradation over multiple cycles. The study also investigated the linear attenuation coefficient (LAC) of the current ferrite nanoparticles, demonstrating increased LAC values with higher Cr content, while the half value layer (HVL) diminished with further Cr concentration. The HVL values indicated the potential efficacy of our nanoferrites as radiation shields when compared to standard radiation shielding materials. Overall, this research suggests a new direction for optimizing spinel nanomaterials for applications in water treatment and radiation shielding.

Enhanced radiation shielding efficiency of polystyrene nanocomposites with tailored lead oxide nanoparticles

In this study, we investigated a novel polymer nano-composite, PS-PbO, containing two distinct nano-sizes of lead oxide nanoparticles (PbO-A and PbO-B), in addition to the bulk size (PbO-K). These nanoparticles were embedded separately in a polystyrene (PS) matrix at different weight percentages (10%, 15%, 25%, and 35%) using roll mill mixing and compressing molding. Our evaluation focused on the radiation attenuation ability of PS-PbO and the effect of particle size, considering gamma-ray energies ranging from 0.06 to 1.3 MeV (from sources like 241Am, 133Ba, 137Cs, and 60Co). The linear attenuation coefficient (LAC) was determined by analyzing samples of the synthesized composite with different thicknesses. Then, various shielding parameters were calculated, including total molecular, atomic, and electronic cross-sections (σmol, σatm, σel), as well as the effective atomic number and the electron density (Zeff and Neff). Surprisingly, modifying PbO particle sizes had a significant impact on shielding efficiency. For instance, the composite with 25 wt% of the smallest PbO-B particles showed a 26.7% increase in LAC at 0.059 keV compared to the composite with 25 wt% of PbO-K (larger particles). Notably, the LAC peaked at low energy (0.059 keV), close to the K-edge of Pb, where interaction is directly proportional to Z4. With increasing PbO concentrations, the LAC of PS-PbO composites increased steadily. Additionally, as PbO concentration increased, the composite’s effective atomic number Zeff and the electron density Neff increased, leading to a greater total Gamma-ray interaction cross-section. Furthermore, when comparing the Half-Value Layers of the novel nanocomposite to traditional lead shielding, a 70% reduction in mass was observed. Notably, the composite containing the smallest nano-size of PbO exhibited the highest radiation-shielding efficiency among all combinations and could therefore be used to create inexpensive and lightweight shields.

Design and characterization of borosilicate glass modified with TiO2 for enhanced optical and radiation shielding applications

This work investigates the potential of borosilicate glass doped with titanium dioxide (TiO2) for radiation shielding applications. The study explored the impact of varying TiO2 concentrations on the glass structure, optical properties, and radiation shielding effectiveness. X-ray diffraction (XRD) and Raman spectroscopy confirmed the amorphous nature of the glasses. The addition of TiO2 affected the glass network structure, as evidenced by changes in the Raman spectra and density measurements. UV–Vis spectroscopy revealed a red shift in the absorption edge (416–481 nm) and a decrease in the indirect optical band gap (2.91–2.70 eV) with increasing TiO2 content. The refractive index also increased from 2.54 to 3.54 with TiO2 concentration. The mass attenuation coefficient (MAC) and linear attenuation coefficient (LAC) increased significantly with TiO2 addition, indicating enhanced radiation attenuation capability. The inclusion of TiO2 reduced the half-value layer (HVL), tenth-value layer (TVL), and mean free path (MFP), while increasing the effective atomic number (Zeff). The effective electron density (Neff) and effective conductivity (Ceff) showed a slight increase with TiO2 content. Energy build-up factors (EBF and EABF) indicated a higher rate of radiation intensity increase and energy absorption within the glass due to the presence of TiO2. Finally, the incorporation of TiO2 into borosilicate glass offered a promising approach to developing improved optical and radiation shielding glasses.

An in-depth analysis of the optical and radiation shielding characteristics of PbF2-MoO3-Bi2O3-B2O3 glasses

This study investigates the optical and radiation shielding characteristics of different glass systems, such as PbF2, MoO3, Bi2O3, and B2O3, with varied concentrations of PbF2. The glass samples were manufactured by a melt quenching technique, with a composition of 20 Bi2O3—10 MoO3 - (70-x) B2O3-x PbF2, where x is a value between 0 and 20 mol%. The optical properties were evaluated using UV–vis spectrophotometry, while the radiation shielding parameters were calculated using Phy-X/PSD software. The mass attenuation coefficient (MAC) at 0.015 MeV exhibited an increase from 34.101 to 54.190 cm2 g−1 as the quantity of PbF2 rose. At an energy of 15.0 keV, the effective atomic number (Zeff) increased from 74.11 to 76.63, while the half-value layer (HVL) decreased from 0.00263 cm to 0.00188 cm. The values of the optical band gap (Eg) ranged from 2.577 to 2.105 eV, showing a decrease as the PbF2 content rose. The study shows that these glass structures can be utilized in advanced technological applications that demand higher optical and radiation shielding properties, thanks to their improved characteristics with increasing PbF2 content.

Enhanced gamma-ray shielding capabilities of Bi-Se-Ge chalcogenide glasses: analytical and simulation insights

This study investigates the gamma-ray shielding properties of Bi-Se-Ge chalcogenide glasses using advanced computational tools. The Phy-X/PSD and FLUKA programs were utilized to determine critical shielding parameters such as linear attenuation coefficient ( GLAC ), mass attenuation coefficient ( GMAC ), half-value layer ( GHVL ), mean free path ( GMFP ), and effective atomic number ( Zeff ). Our findings reveal that these glasses exhibit superior shielding capabilities compared to traditional materials. For instance, the GMAC values for the glasses ranged from 101.472 cm2/g to 177.475 cm2/g at a photon energy of 0.015 MeV. Additionally, the GHVL values decreased significantly with increasing Bi content, from 4.082 cm to 3.104 cm at an energy level of 15 MeV. The effective atomic number ( Zeff ) also increased from 36.12 to 53.23 with higher Bi concentrations. These insights, derived from precise computational analysis, highlight the potential of Bi-Se-Ge glasses for applications in radiation protection. The discussion also examines the impact of substituting Bi atoms with Se on the shielding capabilities of the original Bi-Se-Ge glass.Future work will focus on experimental validation of these results to further substantiate our findings.

Boro-tellurite glasses reinforced with ZrO2: Synthesis, structure, physical, optical characteristics as well as γ-ray shielding capacity

In this study, structure, physical, optical characteristics as well as γ-ray protection capacity of boro-tellurite reinforced with ZrO2 glasses with general chemical formula (51-X)B2O3+20TeO2+19CaO+10Li2O + XZrO2 and substitution ratios of ZrO2 = 0, 1, 2, 3, and 5 mol% was investigated. All studied BTZO-X specimens were in non-crystalline state. Density (ρ) of BTZO-X increased from 2.80 g/cm3 to 3.11 g/cm3. Molar volume of BTZO-X declined from 28.85 cm3/mol to 26.89 cm3/mol. The absorption peak of BTZO-X samples shifted towards a red shift (longer wavelengths). The optical density (OD) enhanced, while the skin depth (ϕ) decreased as a function of photon energy. The mass-absorption (MAC) values accomplished the order; MAC (BTZO-5) > MAC (BTZO-3) > MAC (BTZO-2) > MAC (BTZO-1) > MAC (BTZO-0). Half-value layer and mean free path (MFP) verified the conditions; (BTZO-5)HVL,MFP < (BTZO-3)HVL,MFP < (BTZO-2)HVL,MFP < (BTZO-1)HVL,MFP < (BTZO-0)HVL,MFP. Results concluded that the suggested glass matrix can be used in optical and radiation shielding applications.

Compositional impacts of high CdO content on the structure and radiation shielding efficiency of CoO–Na2O–B2O3 glass system

Here, this study investigated the structural changes and radiation shielding efficiency of a borate glass host modified by varying cadmium oxide (CdO) concentrations. The glass composition consisted of boron oxide (B2O3; 80:56 mol%), sodium oxide (Na2O; 19.6 mol%), and cobalt oxide (CoO; 0.4 mol%), with cadmium oxide (CdO; 0:24 mol%). The glass structure was analyzed utilizing mass density and FT-infrared spectroscopy (FTIR) in the 400 to 1600 cm−1 range, while radiation shielding properties were investigated utilizing the online Phy-X software in the 0.284–1.333 MeV energy window. Notably, the addition of CdO significantly impacted the glass density, increasing it by approximately 93 % as the added CdO concentration rose from 0 to 24 mol% (i.e., from 2.507 g/cm3 to 4.849 g/cm3). FTIR analysis revealed a concurrent increase in BO4 structural units with increasing CdO/B2O3 ratios. This observation was supported by the calculated N4BO4/(BO3+BO4) ratio, which increased from 40.73% for the CdO-free sample to 52.00% for the highest CdO content. This increase in BO4 units, denser than BO3 units, explains the observed density increase. Conversely, the concentration of non-bridging oxygens decreased from 10.14% to 4.34% with increasing CdO contents, indicating a more tightly packed glass network. Radiation shielding studies demonstrated that increasing CdO concentration from 0 to 24 mol% enhanced the shielding efficiency, evidenced by a decrease in the half-value layer parameter (HVL). The radiation protection efficacy (RPE) also increased from 0.214 to 0.426 for the CdO-free sample to the sample containing 24 mol% CdO at the investigated energy level. This finding highlights the superior shielding capability of the CdO-rich sample. Furthermore, the transmission factor (TF) was investigated for a constant thickness of 0.75 cm for glasses. The CdO-rich sample exhibited a lower TF compared to the CdO-free sample, particularly at lower energies. This finding confirms that, for a given thickness and energy, raising the cadmium oxide content in the current composition leads to an observed mitigation in the transmitted radiation.

The effect of rare earths (Nd3+, Er3+, Yb3+) additives on the radiation shielding properties of the tungsten oxide modified tellurite glasses

Abstract In this study, we have reported on the effect of the rare earth oxides on the radiation protection performance of the tellurite glasses. In order to determine the effect of rare earth oxides on the radiation shielding properties of tungsten oxide (WO3) modified tellurite glasses, three rare earth element oxides (Nd2O3, Yb2O3, and Er2O3) have been selected. The glass systems have been synthesized using the traditional melt quenching method and were doped with the different amount (1 %, 3 %, 5 %) of the oxides of rare earth elements (Nd2O3, Yb2O3, Er2O3). The linear attenuation coefficient, mass attenuation coefficient, half value layer, and effective atomic number of the synthesized samples were experimentally measured for 662, 1,173 and 1,332 keV gamma-ray energies which were emitted from 137Cs and 60Co radioactive sources. Measurements were conducted in narrow beam transmission geometry using a NaI(Tl) scintillation detector. In addition, all these parameters were calculated theoretically using the WinXCOM program in the energy region of 0.015–15 MeV. The addition of different types and amounts of rare earth oxides to the tellurite glass system was found to significantly enhance the radiation protection performance of the glasses. In particular, it was found that the radiation shielding characteristics of the glasses improved with increasing amount of rare earth doping, the TWYb5 glass system had the best radiation shielding properties, and there was a trend among the doped rare earth oxides in the form of Yb &gt; Er &gt; Nd according to their radiation shielding performance.

Cerium oxide-reinforced Fe2O3–Na2O–SiO2–B2O3 glass matrix for protection against ionizing X and gamma rays

Radiation shielding glass is an interesting material in the field of radiation shielding due to its remarkable features. In the present paper, we investigated the physical properties of radiation-shielding glass materials that consist of sodium oxide (Na2O), cerium oxide (CeO2), and iron oxide (Fe2O3) incorporated into borosilicate glasses with the formula 90SiO2-(70-x)B2O3+ 20Na2O–1Fe2O3-xCeO2 (CeFeNaBS-glasses). One of the distinguishing characteristics of this glass system is its enhanced radiation shielding capabilities. The structural studies indicated a gradual rise in glass density from 1.954 to 2.658 g/cm with further CeO2 doping. Optical studies showed that the optical band gaps went down from 3.41 eV to 3.33 eV as the amount of CeO2 in the CeFeNaBS-glass matrix rose. The decrease in optical band gap has been correlated with the rising basicity. Also, the increased basicity behavior induces more conversion of Ce3+ to Ce4+ ions by losing a 4f electron. Moreover, with further CeO2 additions, the glass color changed from light brown to dark brown. The presence of Ce4+ ions with further CeO2 additions is responsible for this color transformation. The linear and non-linear refractive indices exhibit enhanced behaviors with higher CeO2 concentrations. We used declining basicity and polarizability behaviors to describe this behavior. The incorporation of larger CeO2 concentrations enhances the ability to improve radiation shielding properties, as demonstrated by the increased values of the mass attenuation coefficient and half-value layer, especially in the energy ranges of soft tissues X-ray and hard tissues X-ray. Hence, the investigated CeFeNaBS-glasses exhibit enhanced transparency and radiation shielding capabilities, rendering them highly suitable for implementation in this domain.

Comprehensive analysis of physical, mechanical, thermal and attenuation characteristics of NaF - B2O3 – Bi2O3 - Sm2O3 glasses for gamma radiation shielding applications

A glass system with the nominal composition 10NaF - (89-x)B2O3 - xBi2O3 - 1Sm2O3 (where x = 15, 20, 25, 30, and 35 mol%) has been fabricated by the melt quenching technique. Densities increased from 3.598 to 4.726 g/cm³ and a corresponding rise in molar volume from 35.880 to 44.089 cm³/mol. The decrement in oxygen packing density (OPD = 75.250–61.239 mol/cm3) and increment in oxygen molar volume (13.289–16.329 cm3/mol) indicate an expansion of the glass structure with the Bi3+ ions. Young's modulus decreases from 58.974 to 41.685 GPa as the concentration of Bi2O3 increases from 15 to 35 mol%. The linear attenuation coefficient (LAC) shows an increasing trend, demonstrating improved attenuation ability with a higher molar concentration of Bi₂O₃. As the Bi₂O₃ concentration increases in the glass matrix, the effective atomic number (Zeff) increases from 61.214 to 72.116 at 59.54 keV, and from 15.829 to 25.988 at 662 keV. The half-value layer (HVL) decreases as bismuth oxide is introduced into the glass matrix, and prepared glasses exhibit lower values than Hematite-Serpentine Concrete, Ilmenite-Limonite Concrete, Basalt-Magnetite Concrete, Ilmenite Concrete, RS253, 55B2O3:20BaCO3:19.5ZnO:5Bi2O3:0.5Dy2O3, RS 323, LSGB1, and LSGB2 shielding materials. The mean free path (MFP) values reduced from 0.094 to 0.053 cm at 59.54 keV, and from 2.958 to 2.073 cm at 662 keV with the Bi2O3 concentration. Consequently, the prepared glass can be reliable for gamma radiation shielding applications.

Enhancing the radiation shielding performance of polyepoxide composites based on cement bypass dust

In this study, radiation shielding composite materials were created by combining epoxy with cement bypass dust (CBPD) at different weight percentages (0%, 10%, 20%, and 30%). The solution casting technique was employed to construct these materials. The FTIR spectra confirmed the formation of the composites and the production of complexes. The morphology and elemental content of the produced composite samples were illustrated using SEM pictures and EDX spectra. In addition, the research findings demonstrated that the composites exhibited improved resistance to changes in temperature as the loading of CBPD increased. The gamma-ray attenuation coefficients of composites consisting of Epoxy + x% CBPD exhibited an increase, along with an increase in the neutron removal cross-section. However, there was a gradual increase in both the mean free path (MFP) as well as the half value layer (HVL) with increasing energy. Additionally, the experimental and theoretical data for attenuation parameters were compared using the Phy-X/PSD software. The relationship between the effective atomic and electron numbers of the Epoxy + x% CBPD composites has been studied. The values of fast and thermal neutron attenuation were analyzed using the NGCal software. In general, these composites are appropriate for use in radiation shielding applications.

Effect of gold nanoparticle dispersion on the structural, optical and radiation shielding parameters of sodium borate glass

Borate-derived radiation shielding glasses have been thoroughly explored, yet the effects of gold nanoparticle (GNP) dispersion on sodium borate glasses remain unstudied. This study investigates the impact of GNP dispersion and varying GNP concentrations on the radiation shielding properties and other parameters of sodium borate glass. All the glasses were prepared using the melt-quench technique with a composition of 30Na2O-70B2O3, containing 0, 2 × 10−10, and 2 × 10−9 mol% of nanoparticles. The x-ray diffractogram (XRD) confirmed the amorphous nature of the prepared glass samples, while Fourier Transform Infrared Spectroscopy (FTIR) confirmed structural modifications, indicated by the formation of non-bridging oxygens due to the incorporation of GNPs. High-resolution transmission electron microscopy (HR-TEM) confirmed the presence of GNPs with an average size of 1.317 nm, and Field Emission Scanning Electron Microscopy (FESEM) revealed further coagulation of GNPs into tiny grains to alleviate surface stresses. Density measurements showed a clear decrease from 2.3051 to 2.1363 g cm−3 with the incorporation of gold nanoparticles. Additionally, a localized surface plasmon resonance peak centered at 612 nm was observed in the UV–Vis spectrogram of the glass with the highest GNP concentration. Radiation shielding parameters, including the mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), and effective atomic number (Zeff), were analyzed using Phy-X/PSD software. The LAC value initially decreases from 76.073 to 70.502 cm−1 with the incorporation of GNPs but increases to 75.878 cm−1 with a higher GNP concentration. This glass system exhibited superior radiation shielding parameters compared to various reported glass systems, indicating its potential for shielding applications.

Evaluation of experimental and simulated gamma ray shielding ability of ZnCo2O4 and ZnCo2O4/graphene nanoparticles

Pristine zinc cobaltite (ZnCo2O4) and graphene zinc cobaltite nanoparticles (NPs) have been successfully synthesized by hydrothermal method. The physical properties of both structures were studied using field emission scanning electron microscopy (FESEM), energy dispersive X-ray spectroscopy (EDX), Fourier transform infrared spectroscopy (FTIR) and X-ray diffraction (XRD). XRD results indicated a formation of spinel structure. The elemental composition of the samples has been determined through EDX analysis. From morphological investigation, the aggregation of grains and nano-sized quasi-spherical grains was observed. Nuclear radiation protection investigation for gamma-ray has been studied for both samples. The protection factors against gamma rays, including linear attenuation coefficients (LAC), mass attenuation coefficients (MAC), transmission Factor (TF), radiation protection efficiency (RPE) mean free path (MFP), half value layer (HVL) and tenth value layer (TVL) were calculated. In addition to the experimental examination, simulation with GEANT4 simulation code was also used for both samples to examine the shielding parameters. The most essential parameters of gamma shielding factors such as mass attenuation coefficients (MAC), mean free path (MFP), half value layer (HVL), tenth value layer (TVL) and linear attenuation coefficients (LAC) were evaluated both practically and by simulation. Practically, these values were: 0.75/0.78 cm2/g, 0.22/0.20 cm, 0.15/0.14 cm, 0.50/0.47 cm, and 4.55/4.86 cm−1, for ZnCo2O4 and ZnCo2O4/graphene samples, respectively. By simulation, these values were: 0.65/0.70 cm2/g, 0.25/0.22 cm, 0.17/0.16 cm, 0.59/0.52 cm, and 3.91/4.38 cm−1, for ZnCo2O4 and ZnCo2O4/graphene samples, respectively. The results show that the presence of graphene has affected all the protection parameters. Keywords: Zinc cobaltite, structural properties, gamma shielding, hydrothermal method.