Radiation Shielding Capability Research Articles

A first-time fusion of TiNbWMoZrOx high entropy oxide (HEO) with zinc-tellurite glass: Toward superior physical properties

While numerous oxide additives have traditionally been employed to enhance the radiation shielding capabilities of glasses, the unique attributes of high-entropy oxides (HEOs), a group of materials acclaimed in contemporary material science for their distinctive properties have remained unexamined in this specific area. This novel study explores the enhancement of radiation shielding properties in zinc-tellurite glasses through the integration of TiNbWMoZrOx High Entropy Oxides (HEO). Utilizing advanced synthesis techniques, including mechanical alloying and oxidation, the research successfully incorporates HEOs into glass matrices, aiming to improve gamma-ray and neutron attenuation. Characterization through X-ray diffraction (XRD), scanning electron microscopy (SEM), and X-ray photoelectron spectroscopy (XPS) confirms the uniform distribution and structural integrity of the HEOs within the glasses. The synthesis of glass samples with a base structure suitable for the molar composition of 25ZnO.75TeO2 (mol%) and glass samples doped with TiNbWMoZrOx (HEO) was carried out using the traditional high-temperature melting and annealing method. The outcomes demonstrate a concentration-dependent increase in shielding efficacy, particularly highlighting the superior performance of glasses doped with 4 mol% of TiNbWMoZrOx (HEC2–4), which exhibit significantly enhanced mass attenuation coefficients, lower half-value layers, and higher effective atomic numbers. This indicates the effective role of HEOs in boosting radiation protection capabilities. Comparative analysis with traditional shielding materials showcases the HEC2–4 glasses' competitive advantage, underlining their potential as a versatile shielding solution. It can be concluded that incorporating TiNbWMoZrOx high entropy oxides into zinc-tellurite glasses significantly augments their radiation shielding properties, offering a novel approach for enhancing protection against gamma-ray and neutron in various applications.

Microstructure, thermal and radiation shielding properties of aluminium‐silicon‐boron alloy prepared by mechanical alloying

AbstractThis study focused on developing microstructural, thermal, and radiation shielding changes in Al50Si25B25 powders using mechanical alloying techniques. Based on the x‐ray powder diffraction data, the crystallite size and microstrain of the 100‐hours milled powder were calculated as 0.25 nm and 50.33 %, respectively. The solubility of silicon in the α‐aluminium matrix increased with longer mechanical alloying duration. Transmission electron microscope analyses further showed that the alloy particulates had an average size of 3 μm and an average grain size of 0.226 nm. The radiation shielding properties of the Al50Si25B25 powders indicated that the Linear Attenuation Coefficient value increased from 0.0554±0.1689 cm−1 to 1.0632±0.2425 cm−1 with an increase in the thickness of the Al50Si25B25 alloy. This work successfully demonstrated the potential of mechanical alloying techniques to enhance the microstructural and thermal properties of Al50Si25B25 powders. It highlighted their effectiveness in providing radiation shielding capabilities when varying the thickness of the alloy.

Mechanical and, photon transmission properties of rare earth element (REE) doped BaO–B2O3–Li2O–Al2O3–P2O5 glasses for protection applications

This study explores the dual functional capabilities of rare earth (REE) doped BaO–B2O3–Li2O–Al2O3–P2O5 glasses, with an emphasis on the 1.50Dy-Tb-Eu composition, previously recognized for its superior luminescent properties. By employing Monte Carlo simulations and Phy-X/PSD software, we have methodically evaluated the gamma-ray and neutron shielding efficacies of these materials. Our key findings indicate that the 1.50Dy-Tb-Eu sample not only excels in luminescence but also demonstrates superior gamma-ray shielding, characterized by low exposure buildup factors, and other related properties across varying energy spectra. Furthermore, the Tb-Eu3.0 variant, enriched with the highest Europium (Eu) content among the bi-REE doped glasses, exhibited the most effective neutron attenuation. Additionally, our investigation into the mechanical properties of these glasses, through the estimation of their Elastic Moduli using a mixture rule approach, revealed a significant enhancement in stiffness with the incorporation of Dy, Eu, and Tb. The mechanical properties were evaluated using a mixture rule approach to estimate the Elastic Moduli. This highlights the crucial role of these dopants in not only improving the luminescent and radiation shielding capabilities but also in strengthening the mechanical integrity of the glasses. The study substantiates the premise that the integration of specific REE elements significantly enhances the glass materials' shielding properties without compromising their luminescent functionality. The obtained findings would be significant for implications on the development of advanced materials tailored for industries where high optical quality, effective radiation protection, and robust mechanical properties are paramount. It can be concluded that Dy-Tb-Eu incorporation into BaO–B2O3–Li2O–Al2O3–P2O5 glasses can be considered as a monotonic strategy to achieve a harmonious balance between luminescence, radiation shielding, and mechanical performance.

Microstructure and radiation shielding characteristics of PVA fiber-reinforced ultra-high performance concrete

The application of nuclear technologies simulates the development of radiation shielding materials. Traditional heavy-weight concrete used for radiation shielding is limited in practical construction due to the poor mechanical properties and durability. This study developed a PVA fiber-reinforced ultra-high performance concrete (UHPFRC) with magnetite as heavy aggregates used for radiation shielding. Due to the scientific skeleton design, UHPFRC exhibits superior mechanical properties, with compressive strength and flexural strength reaching up to 121.9 MPa and 23.2 MPa, respectively. The microstructure of UHPFRC was investigated in detail and the results revealed that the incorporation of PVA fibers refined the pore structure of UHPFRC. The interfacial transition zone between magnetite aggregates and cementitious matrix in UHPFRC was much denser than that in traditional concrete due to the low water to binder ratio. The gamma and neutron radiations shielding capacity of UHPFRC were evaluated by the combination of actual measurement and simulation. By introducing light nuclei and refining the pore structure, the incorporation of PVA fibers improved the neutron radiation shielding capabilities of UHPFRC by 5.1%.

Characterizing of PVA/CMC/MWCNTs nanocomposite films doped Zn0.9Ni0.1S nanoparticles for comprehensive γ-ray radiation shielding performance

Nanocomposite films were prepared from Carboxymethylcellulose (CMC), Polyvinyl alcohol (PVA) polymers and multi-walled carbon nanotubes (MWCNTs) using the casting technique. The resulting PVA/CMC/MWCNTs nanocomposite films have been incorporated with various concentrations of the Zn0.9Ni0.1S nanoparticles. The γ-ray radiation shielding capabilities of the films were discussed in details for various gamma sources using the Phy-X/PSD software in the energy range (0.015–15 MeV). The linear (LAC) and mass (MAC) attenuation parameters, the half-value layer (HVL), the tenth value layer (TVL), the effective atomic number (Zeff) were determined. The γ-ray buildup factors, were also determined for different penetration depths in the range (0.5–40 MFP). Results showed that, the shielding parameters are greatly affected by the density of the samples and the PVA/CMC/MWCNTs samples have the highest shielding ability in the energy region ranges (0.015–0.2 MeV) and (5–15 Mev). The structural and chemical characteristics of the films and the nanoparticles were examined using X-ray diffraction technique. The films elemental composition and morphology were discussed using energy-dispersive X-ray spectroscopy (EDX) and scanning electron microscope (SEM) techniques, respectively. The linear and nonlinear optical properties, including the extinction coefficient (K), the energy gap (Eg), the refractive index (n), the dielectric parameters, nonlinear susceptibilities(χ(1), χ(3)) and nonlinear refractive index (n2), were discussed by UV–Vis spectroscopy's absorbance and transmittance spectra. A reduction in Eg values from 4.55 eV to 4.5 eV and 4.41 eV for films doped with 1 wt% and 3 wt% of Zn0.9Ni0.1S. The uniform distribution of the added nanoparticles at 5 wt% has been confirmed. The energy dispersion parameters confirmed a higher probability of electronic transitions at low energy due to the intermolecular modifications.

Developing green slag/bentonite-based geopolymers modified with meso-porous tungsten oxide: Zeolitic phases, mechanical performance and gamma-radiation mitigation

In an attempt to maintain the sustainable development goals in the construction sector via reducing the raw-materials/energy consumption and greenhouse-gas emissions related to cement production, a green nano-modified slag/bentonite-based alkali-activated material was developed. Firstly, the green composites were prepared by mixing slag and bentonite with a ratio of 2:1. Several factors like NaOH-concentration (6, 8, 10 wt%); thermal treatment of bentonite (as-received “RB” and thermally treated at 650 °C “TB”); curing conditions (normal-curing for 3 and 28-days as well as hydrothermal-curing at 3, 6, 9, 15 bar for 4 h) and meso-porous tungsten oxide nano-particles “WO3-NPs” inclusion (0.25, 0.5 and 1 wt%) were studied to assign the optimum conditions for fabricating composites with adequate mechanical properties and radiation-shielding ability. The mechanical performance and radiation shielding were evaluated by measuring the compressive-strengths and linear attenuation coefficient “μ”/ half value layer “HVL” using 137Cs, respectively. The results reveal the feasibility of using 8 wt% NaOH, TB, hydrothermal-curing at 3 bar/4 h and 0.5 wt% WO3-NPs in fabricating low-cost/pre-cast/environmentally friendly building material with superior compressive-strength (53.6 MPa). Also, the radiation shielding results substantiate that this developed composite achieved adequate μ and HVL values, referring to its efficiency as a radiation-blocker. The synergistic impact of alkali-hydrothermal-activation, the high pozzolanicity of TB and the nucleation-site/potential-seeds effect of WO3-NPs are the main reasons behind forming strength-giving-phases from stratlingite, hydrogarnet, analcime and pentasil zeolitic phase (ZSM-5), as proved by X-ray diffraction (XRD), thermogravimetric analysis (TGA/DTG) and scanning electron microscopy (SEM). The presence of such phases reinforced the microstructure, thus improving the mechanical performance and radiation shielding capability.

Preparation and radiation shielding features of high density, transparent borosilicate glasses with different Bi2O3 contents

This work assessed highly effective bismuth borosilicate glasses' nuclear radiation shielding capabilities in terms of different concentrations of Bi2O3. Melt-quenching was the method used to create the glasses. The Phy-X/PSD program was used to compute the μm values. The bismuth borosilicate glasses' nuclear radiation shielding properties were determined in the 0.015–15 MeV energy range. Increasing Bi₂O₃ concentration resulted in an increase in mass attenuation coefficient, linear attenuation coefficient, and effective atomic number. Conversely, the half value layer and mean free path values decreased. The B48Bi17 sample, with its largest Zeff, is a great gamma attenuator. The results of a new study may help to clarify the nature of the Bi2O3 additive used in borosilicate glasses, which are a potential form of shield for use in industrial and medical radiation facilities.

Decoding the role of bismuth oxide in advancing structural, thermal, and nuclear properties of [B2O3–Li2O–SiO2]-Nb2O5 glass systems

This paper investigates the pivotal role of bismuth oxide (Bi₂O₃) in the enhancement of nuclear safety, structural, and thermal properties of glasses, specifically in the BNLS system. BNLS system has the formula [B2O3–Li2O–SiO2]-Nb2O5(20-x)–(Bi2O3)x (where x = 0.0,5.0,10.0,15.0 and 20.0 mol%). Through a comparative study, the potential advantages, and limitations of integrating Bi₂O₃ in place of traditional elements are highlighted, emphasizing its importance in the field of advanced glass materials. FTIR analysis showed the presence of Bi–O vibrations of the tetrahedral [BO4] groups and the Bi–O–Bi linkages. DSC testified the glass formation with increasing thermal stability of the formed glass with the inclusion of Bi2O3 into the glass system. Through the quantification of the Gamma Linear Attenuation Coefficient (GLAC) and Gamma Mass Attenuation Coefficient (GMAC), the work identifies the attenuation behavior against varying photon energies. Notably, a concentration-dependent rise in attenuation characteristics is observed, with BNLS20 exhibiting the most potent radiation shielding. Glass Half-Value Layer (GHVL) parameters and Mass Gamma Photon Penetration (GMFP) were measured, reinforcing that glasses with higher Bi2O3 concentrations and lower GHVL are better attenuators. The transmission factor (ln(I/Io)) was also studied, confirming that BNLS20 possesses the most effective radiation shielding capabilities. This research establishes that adding Bi₂O₃ to the [B2O3–Li2O–SiO2]-Nb2O5 glass system markedly improves its thermal stability and radiation shielding capabilities. BNLS20, in particular, emerges as a standout for radiation protection, surpassing both other BNLS variants and conventional shielding materials, thereby positioning it as an exceptional choice for advanced nuclear safety applications.

Efficacy of barium and calcium additives in lithium silicate glasses for nuclear shielding applications

This study presents a detailed investigation into the nuclear radiation shielding capabilities of lithium silicate (Li2O-SiO2) glass systems, specifically examining the impact of doping with barium oxide (BaO) and calcium oxide (CaO). Utilizing advanced simulation tools, including PAGEX and SRIM for charged particle interactions, and Phy-X/PSD for gamma-ray attenuation analysis, the radiation shielding effectiveness of BaO-based and CaO-based lithium silicate glasses were systematically compared. The gamma attenuation parameters (LAC, MAC, TVL, HVL, EBF, EABF, MFP, Zeff, Neff, FNRCS, and Zeq) of investigated glass samples were computed via the Phy-X/PSD program (15 keV-15 MeV energy). The HVL values vary between 0.007–14.203 cm, and the TVL values vary between 0.054–47.182 cm for all samples in the selected energy range. The highest and lowest values of FNRCS were observed for samples BaO20 and CaO5, with the values 0.093 and 0.1 cm−1, respectively. KERMAs were calculated using PAGEX software between the 1.5 keV and 20 MeV energy range, with the highest KERMA obtained for the BaO20 sample at 0.05 MeV and the lowest KERMA obtained for the CaO5 sample at the lowest density. The mass stopping power quantities were computed between 1 keV-10 GeV energy with PAGEX. The projected range values were calculated with SRIM codes. The lowest projected range values for both alpha particles and protons were obtained for the BaO20 sample with maximum density (3.391 g cm−3). The sample with BaO20 code showed better shielding potential for alpha and proton particles with lower values of projected range and mass stopping power. Findings reveal that the Li2O-BaO-SiO2 glass composition exhibits superior gamma-ray attenuation properties compared to its CaO-doped counterpart, with the BaO20 sample demonstrating particularly enhanced performance.

Tailoring glass radiation shielding properties through the Integration of ZnO and CaO

In this study, borate glasses with a general formula of (80-x-y)B2O3–10BaO–10Na2O-xZnO-yCaO, where x = 10, 15, 20 and 25 mol %, and y = 5, 10, 15 and 20 mol % were prepared. The radiation shielding capabilities of the prepared glass system were investigated at a wide energy range of 0.015 MeV–15 MeV. The data reveal that, the values of the mass attenuation coefficient (MAC) vaired between 20.043 and 32.435 cm2/g at 0.015 MeV. The MAC demonstrated that the increase of the ZnO and CaO content within the glasses leads to increase the MAC values, and improve the absorption ability of the glasses. The relation between the density of the glasses and their linear attenuation coefficients (LAC) were studied. A positive linear relationship between LAC and density has been fond. At 0.150 MeV, the LAC values are 0.804, 0.874, 0.945, and 1.020 cm−1 for the glass with 5, 10, 15 and 20 mol % of CaO in the order, respectively. We also evaluated the ratio of half value layer (HVL) for all prepared glass samples with lowest and highest density. The results revealed that the calculated ratio of HVL is always >1. This means that the Zn25Ca20 sample requires a smaller thickness to attenuate the same number of photons as betweenZn10Ca5. This is desirable in situations where space is a constraints well as costs as a smaller material can be used. This study uniquely highlights the combined impact of ZnO and CaO on enhancing the radiation shielding performance of borate glasses, offering a novel approach to developing more efficient materials.

Iron borophosphate glasses: Merging optical transparency, structural integrity, and radiation shielding efficacy for sustainable uses

The research work explored the influence of iron doping on the optical behavior, structural characteristics, and radiation shielding capabilities of soda lime borophosphate glass system of composition xFe2O3-(42.5-x)B2O3-26CaO-28.7Na2O-2.8P2O5 (x up to 8 mol%). The glass samples doped with varying iron concentrations were synthesized via the conventional melt-quenching method. A comprehensive characterization approach was employed, integrating X-ray diffraction (XRD) analysis to probe the structural aspects, Fourier transform infrared (FTIR) spectroscopy to examine the molecular vibrations and bonding, and UV–visible spectroscopic techniques to investigate the optical properties. Furthermore, the study evaluated the potential of these iron-doped glasses as effective radiation shielding materials by assessing their attenuation performance against various radiation types. The influence of iron oxide (Fe2O3) addition on the borophosphate network, coordination environment, and optical absorption was examined. The radiation shielding characteristics, such as mass attenuation coefficient, half-value layer, mean free path, and other parameters, were assessed using Phy-x freeware program calculations. The results revealed the formation of an amorphous glass structure and the incorporation of iron ions into the borophosphate network. The addition of Fe2O3 influenced the borate superstructural units, the conversion of BO3 to BO4 units, and the optical absorption bands. The glasses exhibited promising radiation shielding properties combined with increasing Fe2O3 content.

Influence of WO3 replacement for CaO on physical, optical, and γ-ray protection properties of borotellurite glasses: A comparative study

Glasses with WO3 in place of CaO with the chemical formula 45B2O3+15TeO2+(18-X)CaO+22Na2O + XWO3: X = 0 (W-0), 1.5 (W-1.5), 3 (W-3), 4.5 (W-4.5), and 6 (W-6) mol% were prepared using the melt quenching method. A comprehensive study of the structural, physical, optical, and γ-ray protection properties of the prepared glasses was investigated. Density (ρ), molar volume (Vm), UV–Vis measurements, the MCNP5 simulation code, and PhX software were employed to achieve the aims of this study. The density (ρ) of the W-X samples increased slightly from 2.45 g/cm3 to 2.62 g/cm3 as WO3 content increased from 0 to 6 mol%. The molar volume (Vm) evinced the same trend as ρ. In the UV range, significant absorption was observed, rising as the molar concentration of WO3 increased. The direct optical gap (Eopt.(dir.)) declined from 3.59 eV to 3.24 eV, while the indirect gap (Eopt.(indir.)) declined from 3.27 eV to 2.36 eV. The Urbach energies (ΔE) ranged from 0.35 to 0.71 eV. The refractive index (n) increased from 2.33 to 2.59 as WO3 content increased. The molar polarizability (αm) and molar refractivity (Rm) increased. The linear-attenuation absorption (μ) order is: W-0 < W-1.5 < W-3 < W-4.5 < W-6. The W-6 glass sample possessed the lowest half- (HVL), and tenth- (TVL) value layer, as well as the lowest mean free path (MFP). Therefore, the W-6 glass sample offers the best gamma radiation shielding capability among the prepared W-X glasses. Within the investigated energy range, the effective atomic number (Zef) varied from 30.773 to 13.234, 35.398–13.969, 39.089–14.670, 42.103–15.338, and 44.611–15.977 for the W-0, W-1.5, W-3, W-4.5, and W-6 glasses, respectively. At 0.080 MeV, the mass-attenuation absorption (μm) of the investigated W-X glasses was higher than for TBLMC-X (TeO2–B2O3–Li2O–MoO3–CuO) and TS-X (9SiO2–Al2O3–Na2O–B2O3–TeO2) glasses.

3D Printing of Composite Radiation Shielding for Broad Spectrum Protection of Electronic Systems.

The miniaturization of satellite systems has compounded the need to protect microelectronic components from damaging radiation. Current approaches to mitigate this damage, such as indiscriminate mass shielding, built-in redundancies, and radiation-hardened electronics, introduce high size, weight, power, and cost penalties that impact the overall performance of the satellite or launch opportunities. Additive manufacturing provides an appealing strategy to deposit radiation shielding only on susceptible components within an electronic assembly. Here, a versatile material platform and process to conformally print customized composite inks at room temperature directly and selectively onto commercial-off-the-shelf electronics is described. The suite of inks uses a flexible styrene-isoprene-styrene block copolymer binder that can be filled with particles of different atomic densities for diverging radiation shielding capabilities. Additionally, the system enables the combination of multiple distinct particle species within the same printed structure. The method can produce graded shielding that offers improved radiation attenuation by tailoring both shield geometry and composition to provide comprehensive protection from a broad range of radiation species. The authors anticipate this alternative to traditional shielding methods will enable the rapid proliferation of the next generation of compact satellite designs.

Effect of temperature on gamma radiation shielding capabilities of bauxite-based refractory concrete

This work presents experimental and theoretical studies on gamma-ray shielding capabilities of bauxite-containing refractory concretes containing new types of inorganic cements belonging to the CaO-Al2O3 (as a reference), CaO-BaO-Al2O3-ZrO2 and CaO-Al2O3-Fe2O3-ZrO2 systems. Firstly, the structure, microstructure, hydration behavior of cements, and thermal stability analysis of hydration products were investigated using X-ray diffraction, scanning electron microscopy/energy-dispersive X-ray spectrometry (SEM-EDS) and Thermogravimetry-Differential Scanning Calorimetry (TG-DSC) coupled with Evolved gas analysis-mass spectrometry (EGA-MS). When both Fe2O3 and BaO occur in the form of hydraulic phases as Ca2AlFeO5 and BaAl2O4, respectively, or are structurally incorporated into Ca7ZrAl6O18, the iron and barium modify the nature of hydration products of the CaO-Al2O3-H2O-type. Secondly, three types of concretes containing refractory bauxite aggregates were developed and tested in terms of microstructure, phase content, volumetric density, and weight loss. The maximum weight loss at 110 °C was associated mainly with the evaporation of the capillary water and the physically adsorbed water (gel water), whereas the chemically bound water (crystal water) occurring in hydrates was released at higher temperatures. Slight variations of the volumetric density of the concretes due to temperature were found. The CCS of the concretes fell within the standard values of ca. 50–100 MPa for shielding refractory concretes. Finally, the effect of temperature on the gamma radiation shielding capabilities of concretes was evaluated using the transmission method for gamma rays with energy in the range of about 81–1400 keV. The obtained values of the linear and mass attenuation coefficients showed improvement in the shielding properties as compared with ordinary concrete. Moreover, the obtained results show no significant effect of elevated temperature on the gamma radiation attenuation properties of the studied bauxite-based refractory concretes which suggests that they may be very useful as shielding materials in severe thermal working conditions.

Thermal, and radiation shielding properties of SrO–B2O3–TeO2–ZnO–Bi2O3 glasses doped with Dy2O3

The newly proposed materials demonstrated outstanding and effective radiation shielding capabilities and promising mechanical properties. A series of (20-x) SrO-(73)B2O3-(5)TeO2-(1)ZnO-(1)Bi2O3 doped with x-Dy2O3 have been produced employing the traditional melt-quench process, with the concentration of Dy2O3 varying from 0.05 to 1.5 mol%. This research examined glass samples' structural stability, mechanical and thermal characteristics, and radiation shielding capabilities. All of the glasses were amorphous, as confirmed by the X-ray examination, and the glass with the label SBTZBD6 had the maximum density because of the higher Dy2O3 content. The insert of Dy2O3 into the glass composition increased density values from 2.94 to 3.04 g/cm3 for SBTZBD1 and SBTZBD6 and improved mechanical properties such as Poisson ratio and elastic moduli. The hardness Vickers showed the maximum value at 1095.7 HV corresponding to Dy2O3 1 mol%, indicating the influence of Dy2O3 addition on the mechanical properties. The ability of the generated samples to shield against several forms of radiation, such as alpha, proton, neutron, and gamma radiation, was examined using SRIM and Phy-X software. The lowest HVL is 0.009 cm for SBTZBD6 at 0.02 MeV, the highest HVL was observed at 15 MeV with a value equal to 7.066 cm for the same sample. Dy2O3 was used instead of SrO, significantly increasing the μ/ρ values and improving radiation shielding. However, it was discovered that fast neutron shielding experienced a reduction in energy loss per unit mass (mass stopping power) when SrO was replaced with Dy2O3. However, the substitution also reduced energy loss per unit mass for alpha and protons and fast neutron shielding. To sum up, this study's glass samples are highly recommended for ionizing radiation shielding.

Impact of neodymium oxide (Nd2O3) substitution in barium–boron-phosphate glasses: A pathway to superior mechanical, optical, and radiation shielding performance

This study delves into the impact of substituting Nd2O3 for Na2O in Barium–Boron-Phosphate glasses, aiming to enhance their mechanical strength, optical characteristics, and radiation shielding efficacy. Glasses with a composition of 50B2O3 + 20P2O5 + 20BaO + (10-x)Na2O + xNd2O3 (x = 0, 1, 2, 3, 4 mol%) were synthesized and characterized. The findings indicate that as the Nd/Na ratio increases, the density of the glass also rises within the range of 3.77–4.23 g/cm3. Moreover, the addition of Nd leads to notable alterations in the optical characteristics of the resulting glasses. Specifically, there is a shift observed in the UV absorption edges, coupled with a noticeable increase in absorption at visible wavelengths. Moreover, Nd2O3 addition reduced the Urbach energy (from 0.6018 to 0.2239 eV for Nd0-Nd4) and the optical band gap indicating improved electronic structure and decreased disorder. The mechanical properties studied using the Makishima-Mackenzie model show As the replacement ratio of Nd2O3 increases, there is a noticeable improvement in the glass's mechanical robustness. Importantly, Glasses with high Nd/Na ratio in their composition exhibit enhanced radiation shielding capabilities, evidenced by increased mass attenuation coefficients and effective removal cross-sections for photons and fast neutrons, respectively. These findings suggest that Nd2O3-doped glasses offer a promising pathway for developing superior radiation shielding materials with tailored properties for diverse applications in nuclear facilities, medical devices, and space exploration equipment.

Assessment of radiation shielding capability of a high-density TeO2–Tl2O–Ag2O glass system: A simulation and theoretical studies

We investigated the shielding properties of four selected glass samples among the 66 samples. These glass samples had the following compositions and densities: S1 (55TeO2+45Ag2O, density 6.28 g/cm3), S2 (55TeO2+5Tl2O+40Ag2O, density 6.37 g/cm3), S3 (50TeO2+15Tl2O+35Ag2O, density 6.49 g/cm3), and S4 (40TeO2+55Tl2O+35Ag2O, density 7.20 g/cm3). These glasses exhibit high density. We compute the mass attenuation and linear attenuation coefficients for these samples using MCNPX simulations and Phy-X software between 0.001 MeV and 15 MeV energy range. The derived mass attenuation coefficient (MAC) enables the calculation of key radiation shielding metrics. The tenth value layer, the half value layer (HVL), the mean free path (MFP), and the effective atomic number (Zeff) were also determined. Values of LAC values for S1, S2, S3 and S4 glasses span 244.91 to 0.24932 cm⁻1, 319.52 to 0.2625 cm⁻1, 447.24 to 0.28491 cm⁻1 and 379.480 to 0.273 cm−1, respectively. Correspondingly, HVL values range from 0.0028 to 2.78005 cm, 0.0021–2.6403 cm, and 0.00154–2.4327 cm and 0.002135–2.917403 cm for S1, S2, S3 and S4 glasses, respectively. Our findings reveal that results from both MCNPX and Phy-X exhibit consistency, supported by computed relative differences. Notably, the glass sample with a relatively higher TlO2 concentration demonstrates superior shielding properties across the entire energy spectrum. Importantly, these glass samples can significantly lower the strength of the x-rays and γ-rays.

Y2O3 reinforced B2O3–SiO2–BaO–Na2O glass system: A characterization study through physical, optical and gamma / neutron shields characteristics

Glasses with the composition 48B2O3– 13SiO2– 7BaO- (32-x) Na2O-xY2O3, (x = 0, 1, 2, 4, and 8 mol %) were synthesized by the melt quenching procedure. There is good transparency in every glass sample. The increase in density (2.825–3.894 gm/cm3) of the present glasses is what triggered the decline in molar volume (25.41–21.80 cm3/mol) and the decrease in the Boron–Boron distance (0.475–0.452 nm). The estimated values show that Eopt.indi. &Eopt.di are 2.317, 2.672, 2.8, 2.98 and 3.1 eV, 2.69, 2.92, 3.05, 3.25, and 3.44 eV respectively, whereas (Eu) values declined. As the Y2O3 increased the refractive index (nD) increased. (nD) of the synthesized glasses using Eopt.indi.&Eopt.di were estimated. To find the radiation properties of the suggested glasses, the Phy-X/PSD code was employed. We concluded that the current glasses have better radiation shielding capabilities when employed in such fields. As the Y2O3 replacing ratio increased ∑R increased.

Impact of Bi2O3 on the glass system B2O3 -TeO2–MgO–PbO on the purpose of radiation shielding efficacy

In this study, eight glass samples were prepared with the composition of [x Bi2O3-(75-x) B2O3–15TeO2 –5MgO–5PbO; where x = 0, 10, 20, 25, 30, 40, 50, and 60 mol%]. In the composition of those glass samples, various amountsof B2O3 were replaced by Bi2O3 to improve the glass material's radiation shielding capability. The mechanical properties of these glasses have been evaluated using densimeter and microhardness. The Vickers microhardness (Hv) slightly decreases as the amount of Bi2O3 increases due to the formation of Non-Bridging Oxygen (NBO). To evaluate the radiation shielding effectiveness of the prepared glass samples, we performed Monte Carlo simulations of several shielding parameters. The mass attenuation coefficients of the experimentally produced BTMPBi glass series were calculated using NIST and MCNP6, and reasonable agreement was found between the simulation and experimental results. The relative difference between NIST and MCNP6-based results was calculated, and the maximum deviation was 2.21% for the 1173 keV gamma ray incident in the BTMPBi60 glass sample. The value of the mean free path of those prepared glass samples maintained the following trend - BTMPBi0> BTMPBi10> BTMPBi20> BTMPBi25> BTMPBi30> BTMPBi40> BTMPBi50>BTMPBi60. The prepared glass sample BTMPBi0 showed a 2.6 times higher value of the mean free path at energy 1332 KeV compared with the prepared BTMPBi60. Analyzing the composition of the prepared glass samples, it is clear that the greater the amount of Bi2O3 the greater the value of linear attenuation coefficient (LAC) and effective atomic number. Based on the results, it can be concluded that the glass sample containing 60 mol % of Bi2O3 (BTMPBi60) exhibited the highest radiation shielding capability among all of the prepared samples.

Evaluation of incorporation of granite waste and SnO2-NPs into coating mortar for gamma-ray shielding

This study explores the use of waste granite and tin oxide nanoparticles (SnO2 NPs) as replacements for sand in mortar composites containing Ordinary Portland Cement (OPC), Hydrated Lime (HL), and Quarry Sand (QS). Scanning electron microscopy (SEM) imaging revealed an increase in particle distribution between voids in the control mortar, enhancing photon absorption. The density of the prepared mortar samples exhibited a notable increment, with a 2.12–2.30 g/cm3 increase through the inclusion of SnO2-NPs. Additionally, the Phy-X software was employed to experimentally measure and theoretically calculate the linear attenuation coefficient (LAC), demonstrating a high degree of agreement between the two values. The LAC values were found to increase with the replacement ratio of granite waste and SnO2 nanoparticles, demonstrating the effectiveness of these materials as radiation shielding agents. This study investigates the effect of substituting waste granite and SnO2 nanoparticles for sand in mortars, resulting in an increase in LAC levels, indicating potential for improved radiation shielding capabilities, although the degree of change in LAC may be energy-dependent. The half value results (HVL) results demonstrated a significant decrease in required material thickness for radiation shielding applications with numerical values of 1.153, 0.734, 0.456, 0.351, and 0.261 cm for the control, Mor-1, Mor-2, Mor-3, and Mor-4 samples, respectively, at an energy of 0.06 MeV.