Gamma-ray Shielding Properties Research Articles

Radiation shielding properties of heavy-weight concrete and heavy-weight geopolymer concrete incorporating nano-ZnS

The population growth and the subsequent increase in energy demand for buildings require the widespread use of sustainable materials in the construction industry. Therefore, geopolymer concretes (GPC) are expanding with the ability to emit less greenhouse gases (GHG) compared to conventional concrete. In this study, the effect of adding different content of Zinc sulfide nanoparticle (nano-ZnS) 0, 1.5, 3, 4.5, and 6 % by weight of cement on density (ρ), compressive strength, gamma ray radiation protection characteristics, and microstructure based on scanning electron microscope (SEM) is investigated in heavy-weight concrete (HWC) and heavy-weight geopolymer concrete (HGC). The results have shown that nano-ZnS nanoparticles improve the strength and gamma ray shielding properties of HWC and HGC by modifying the microstructure so that by adding the optimal amount of 6 % nano-ZnS, the maximum compressive strength for HWC and HGC was obtained by 57.4 and 41.5 %, respectively. In addition, the highest linear attenuation coefficient (µ)was obtained with the addition of 4.5 % nano-ZnS for HWC and HGC, 12.8 and 8.9 %, respectively.Furthermore, the life cycle assessment (LCA) of the three phases of raw material production, transportation and concrete production has revealed that HGC has emitted 41.5 % less CO2 compared to HWC. In general, HGC in the presence of the optimal amount of nanoparticles has shown a more visible improvement in compressive strength and gamma ray shielding properties. In addition, HGC as an environmentally friendly material, has significantly reduced the emission of CO2.

Synthesis, structural, optical and experimental gamma-ray shielding properties of molybdenum-trioxide reinforced CRT glasses

Synthesis, structural, optical and experimental gamma-ray shielding properties of molybdenum-trioxide reinforced CRT glasses

Optical and gamma ray shielding properties of lead magnesium zinc borate (PMZB) glasses

As the concentration of PbO in PMZB glasses is increased, the result is an elevated density and a reduced molar volume. As the percentage of PbO in the sample grows, the absorption peak in the optical spectrum has moved towards longer wavelength side. Creating non-bridging oxygens leads to a reduced gap in the band energy. When the content of Pb rises, so do the dielectric and optical dielectric constant values and the refractive index, suggesting an enhanced influence of non-bridging oxygens. The non-metallic character is confirmed by the metallization values, which vary from 0.382 to 0.362. Molar refractivity decreases with PbO content. This study conducted an evaluation of the radiation shielding characteristics in the 0.122–1.46 MeV range. The linear attenuation coefficient varied between 11.073 and 15.161 cm−1 at 0.122 MeV. The PMZBX glasses have lesser absorbing capabilities for high energy photons because of their greater penetration abilities. Thus, the PMZB4 glass, which has the greatest PbO content, shows the most promise out of the tested glasses.

Structural, physical, optical, and gamma ray shielding properties of SnO2-based boro-silicate glasses: The influence of substituting Na2O by SnO2

The study focuses on creating new boro-silicate glasses doped with SnO2 for radiation shielding. It examines how substituting Na2O with SnO2 affects their structural, optical, and shielding properties. Density increases from 2.406 to 2.488 g/cm³ with rising SnO2, measured via the Archimedes Method. The examination for the glassy phase was performed using the XRD diffractometer. UV/Vis spectrophotometer analysis reveals reduced refractive index (2.412–1.976) and increased optical absorption-band gap (direct: 3.648–5.662 eV; indirect: 2.994–5.163 eV) with SnO2 concentrations of 0–9 mol.%). The effectiveness of the radiation shielding was assessed over the 0.059–1.408 MeV gamma-ray energy interval. The analysis demonstrates that when the concentration of SnO2 increases, the synthesized glasses' linear attenuation coefficient improves. As the SnO2 content was raised between 0 and 9 mol%, the linear attenuation coefficient rose between 0.489 and 2.892 cm−1 (at energy of 0.059 MeV) and between 0.126 and 0.128 cm−1 (at energy of 1.408 MeV), respectively. As the SnO2 content was raised between 0 and 9 mol%.

Comprehensive study of optical, thermal, and gamma-ray shielding properties of B2O3–SiO2–BeO– MgO–La2O3, glasses

The purpose of this work is to study the thermal, optical, structural, and radiation-shielding features of glass system with composition 57B2O3–16SiO2–11BeO- (16-x) MgO-xLa2O3, x = (0≤x≥16). The structural characteristics of glass samples are examined using XRD. This glass's molar volume decreased from 18.21 to 17.46 (cm³/mol), while its density increased from 3.213 to 5.967 g/cm³. Differential thermal analysis data were used to assess the thermal stability (ΔT) for BSLa samples. It was discovered that when the La2O3 amount increased, the glass stability increased. The optical band gap (Eoptdi), (Eoptindi) and Urbach's energy (Eu) were computed using UV absorption spectra. (Eoptdi) decrease from 4.323 to 3.816 eV and (Eoptindi) decrease from 3.413 to 2.95 eV, whereas (Eu) increase from 0.278 to 0.324 as a result of the changes of borosilicate's structured caused by the addition of La2O3. The examined glasses may be utilized for non-linear optical applications, according to the high (n) and low metallization (M) values. The Phy-X tool was utilized to obtain (MAC), (LAC), and (Zeff) of the suggested glasses within the energies 0.015–15 MeV. The BSLa16 sample achieved the highest values of the (MAC), (LAC), and (Zeff). Consequently, BSLa16 is a good option for gamma-ray shielding applications.

Effect of different metal oxides on the Radiation shielding features of borate glasses

Three zinc barium-borate glasses were produced in the current work, incorporating different metal oxides (MO) (CaO, TiO2, and CuO) via the melt quenching technique under a 1100 °C melting temperature for 60 min. The fabricated samples' density is 4.112 g/cm3, 4.157 g/cm3, and 4.261 g/cm3 for glasses dopped with CaO, TiO2, and CuO, respectively. Additionally, the Makishima-Mackenzie model was employed to evaluate the effect of metal oxides on the fabricated glasses' mechanical properties. The study shows that the glasses with TiO2 have the highest mechanical moduli and microhardness which reach 4.67 GPa. The gamma-ray shielding properties in the 0.033–2.506 MeV energy interval were estimated by applying Monte Carlo simulation. The study demonstrates that the glass samples containing CuO exhibit the highest linear attenuation coefficient (LAC) when compared to the glasses containing Ca and TiO2 compounds. The LAC of the CuO-doped glasses varied between 28.367 cm−1 and 0.163 cm−1 when the photon energy was raised between 0.033 MeV and 2.506 MeV. Also, the study shows good shielding parameters (half-value layer, lead's equivalent thickness, and radiation protection efficiency) for the glasses doped CuO compared to glasses doped Ca and TiO2.

Effect of modified graphene nanosheets on the properties of 222Rn and gamma ray multifunctional shielding polymer composite materials

AbstractDevelopment of shielding materials for 222Rn and γ radiation has crucial implications for ensuring the safety of individuals. This paper reports the synthesis of modified graphene nanosheets (MGNPs) via the reaction of KH560 with graphene nanosheets (GNPs), while melt blending and hot‐press molding technique were used to fabricate a multifunctional polymer composite shielding material, MGNP/WB/PMMA (polymethyl methacrylate). Successful synthesis of MGNP was confirmed by Fourier transform infrared spectroscopy, and scanning electron microscope (SEM) analysis was utilized to assess the distribution of functional fillers within the cross‐section of the polymer composite. Additionally, thermogravimetric analysis (TGA) demonstrated that MGNP and WB particles enhance the thermal stability of the polymer composite materials. Compared to pure PMMA, 98.7% decrease in the radon diffusion coefficient was observed for MGNP1.5 wt%/PMMA composite material. In addition to enhance the radon‐blocking characteristics of the polymer composites, inclusion of WB particles also boosts their shielding capacity against gamma radiation. The 222Rn diffusion coefficient of MGNP1.5 wt%/WB25wt%/PMMA polymer composite material decreased by 99.6% and at energies of 60 KeV, 80 KeV, 122 KeV, 365 KeV, the mass attenuation coefficient (MAC) for the composite material increased by 0.79, 1.97, 0.57, and 0.05 cm2/g, respectively, compared to pure PMMA.Highlights The PMMA composite materials doped with graphene nanosheets demonstrate outstanding resistance to 222Rn. Graphene nanosheets modified by KH560 exhibit favorable dispersion within PMMA. WB can further enhance the radon resistance of MGNP/WB/PMMA composite materials. The polymer composites exhibit excellent 222Rn and gamma ray shielding properties.

Physical and γ-ray shielding properties of Vietnam's natural stones: An extensive experimental and theoretical study

The current work deals with investigation of the gamma ray shielding properties for various natural stones from Vietnam to be applied in the radiation shielding applications. The physical and chemical properties affecting the γ-ray shielding performance were examined. The MH-300A density meter was utilized to measure the density (ρ, g/cm3) of stone samples, as well as the chemical composition of Vietnamese natural stones was measured using the X-ray fluorescence analyzer (Olympus X-5000). The study shows that the increase in Fe + Ca concentrations within the stone samples increases their density (from 2.48 to 2.86 g/cm3) accompanied with a reduction in the porosity (Φ, %) (from 8.23 to 0.15%) and water absorption (K, %) (from 3.42 to 0.05%) factors. Additionally, the increase in Fe + Ca concentrations increases the linear attenuation coefficient (μ, cm−1) of the studied stones, where the Vietnamese marble stone (M 3.1) with the highest Fe + Ca concentration (65.97 wt%) has the highest linear attenuation coefficient which varied between 3.781 and 0.155 cm−1 with raising the gamma ray energy between 0.040 and 1.332 MeV.

An extensive assessment of the impacts of BaO on the mechanical and gamma-ray attenuation properties of lead borosilicate glass

The current work deals with the synthesis of a new glass series with a chemical formula of 5Al2O3–25PbO–10SiO2–(60-x) B2O3–xBaO; x was represented as 5, 10, 15, and 20 mol%. The FT-IR spectroscopy was used to present the structural modification by rising the BaO concentration within the synthesized glasses. Furthermore, the impacts of BaO substitution for B2O3 on the fabricated borosilicate glasses were investigated using the Makishima-Mackenzie model. Besides, the role of BaO in enhancing the gamma-ray shielding properties of the fabricated boro-silicate glasses was examined utilizing the Monte Carlo simulation. The mechanical properties evaluation depicts a reduction in the mechanical moduli (Young, bulk, shear, and longitudinal) by the rising of the Ba/B ratio in the fabricated glasses. Simultaneously, the micro-hardness boro-silicate glasses was reduced from 4.49 to 4.12 GPa by increasing the Ba2+/B3+ ratio from 0.58 to 3.18, respectively. In contrast, the increase in the Ba/B ratio increases the linear attenuation coefficient, where it is enhanced between 0.409 and 0.448 cm−1 by rising the Ba2+/B3+ ratio from 0.58 to 3.18, respectively. The enhancement in linear attenuation coefficient decreases the half-value thickness from 1.69 to 1.55 cm and the equivalent thickness of lead is also reduced from 3.04 to 2.78 cm, at a gamma-ray energy of 0.662 MeV. The study shows that the increase in the Ba2+/B3+ ratio enhances the radiation shielding capacity of the fabricated glasses however, it slightly degrades the mechanical properties of the fabricated glasses. Therefore, glasses with high ratios of Ba2+/B3+ have high gamma-ray shielding ability to be used in hospitals as a shielding material.

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

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

Evaluation of mechanical strength, gamma-ray shielding characteristics, and ITZ microstructural properties of heavyweight concrete using nano-silica (SiO2) and barite aggregates

This research assessed the mechanical performance, gamma-ray shielding, and interfacial transition zone (ITZ) microstructural properties of concrete mixes that incorporate barite coarse aggregates and nanosilica. To achieve this goal, several concrete mixes containing normal coarse aggregate (NC), barite aggregate (BC), and nano-silica/barite aggregates (NSBC) were fabricated. Several properties such as workability, mechanical strength, electrical resistivity (ER), ultrasonic pulse velocity (UPV), chloride migration (RCPT), and gamma shielding were comparatively assessed for these concrete mixtures. In addition, analytical characterizations viz., x-ray diffraction (XRD), Fourier transform infrared (FTIR), scanning electronic microscopy (SEM), and energy dispersive x-ray (EDX) were employed to study the ITZ microstructure at mortar/aggregate interface of concrete mixtures. The results showed that barite concrete incorporating nanosilica (NSBC) exhibited higher density and improved mechanical properties compared to both normal concrete (NC) and barite concrete (BC). Specifically, concrete mixture containing barite aggregate and 3% nanosilica (3NSBC) content exhibited improved impermeability and reduced concrete porosity. The gamma-ray shielding properties for 3NSBC were superior among all concrete mixtures. After 28 days, 3NSBC exhibits higher compressive strength (18.26% and 14.76%) and greater shielding capacity (12.82% and 6.66%) compared to NC and BC, respectively. The analytical characterizations results have demonstrated that nanosilica helps prevent the accumulation of calcium hydroxide in the ITZ by utilizing it to form calcium silicate hydrate. This leads to the development of a more compact and denser microstructure in the ITZ of nano-silica-based barite concrete (NSBC). Furthermore, it was revealed that, the incorporation of nanosilica exceeding 3% led to agglomeration, resulting in a weaker ITZ within the concrete leading to overall reduction in concrete properties.

An extensive benchmark analysis of advanced ceramic-concretes towards strategic material selection for nuclear applications and waste management

Ceramic concretes, with their exceptional durability and ability to incorporate a high percentage of heavy metal oxides, are of critical importance for nuclear radiation facilities, offering superior radiation attenuation characteristics essential for long-term safety and protection. This study presents a detailed evaluation of the gamma-ray shielding properties of various concrete composites, including Standard Concrete and Heavy Concretes (HC series), with densities ranging from 1.94 g/cm3 to 4.54 g/cm3. Utilizing computational methods, we analyzed several gamma-ray and neutron shielding parameters such as mass attenuation coefficients, linear attenuation coefficients, half and tenth value layers, mean free paths, exposure build-up factors, effective atomic number (Zeff), effective electron density (Neff), fast neutron effective removal cross-section (ΣR), and photon transmission factors (TFs). Our research reveals that the shielding efficacy of concrete is intrinsically linked to its density and elemental composition, with higher densities and the incorporation of heavy elements leading to enhanced attenuation capabilities. Among the concretes studied, Limonite with Steel Punch LS-a, which contains 74.53% Fe in its structure, exhibited the lowest transmission factors (TFs) across all tested thicknesses and energy levels (0.662, 1.1732, and 1.3325 MeV), indicating its superior photon attenuation potential. It can be concluded that the concrete samples with a higher Fe (iron) content in their structure demonstrate clear superiority in gamma-ray attenuation properties.

Characterization of glasses composed of PbO, ZnO, MgO, and B2O3 in terms of their structural, optical, and gamma ray shielding properties

The amorphous glasses containing PbO, ZnO, MgO, and B2O3 have been fabricated using the melt quenching technique. The structural properties have been analysed using the Fourier-transform infrared (FTIR) and Raman spectroscopy. Derivative of Absorption Spectra Fitting (DASF) method have been used to estimate the band gap energy from the UV–Vis absorption data which decreases from 3.02 eV to 2.66 eV with increasing the concentration of the PbO.The four glass samples 0.284 and 0.826 MeV showed unique variations in terms of gamma attenuation ability. LZMB4 glass sample proved to be the mist effective in terms of shielding of gamma radiation as it requires little distance compared to LZMB3, LZMB2 and LZMB1 to attenuate. RPE revealed a raise with increase in the thickness of the material and reduces as the energy raises. TF is superior in LZMB1 compared to LZMB2, LZMB3 and LZMB4, confirming that, LZMB4 will attenuate better. The ZEff of the materials was seen falling as the energy increases, confirming that the linear attenuation coefficient of the glass materials decreases when the energy is increased. The results confirmed that, glass material LZMB4 is the best option especially for gamma radiation shielding applications compared to LZMB3, followed by LZMB2, then LZMB1.

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

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

Physical, optical, mechanical and gamma ray shielding properties of Al2O3–PbO–B2O3–SiO2 glasses

Physical, optical, mechanical and gamma ray shielding properties of Al2O3–PbO–B2O3–SiO2 glasses

CaO-enhanced polyester for safety: experimental study on fabrication, characterization, and gamma-ray attenuation

Abstract The current work deals with studying the influence of cheap, widespread CaO on improving the γ ray-protection capacity of the lightweight, sealing polyester. Therefore, polyester composites were filled with different concentrations of CaO fillers. The fabricated CaO-reinforced polyester composites’ density ranged between 1.177 g/cm3 and 1.377 g/cm3, when CaO filler concentrations increased between 0 wt% and 60 wt%, respectively. Fabricated composites’ morphology and chemical composition, as well as CaO fillers’ grain size and distribution, were proved using SEM and EDX spectroscopy. Additionally, the influence of CaO fillers on the gamma-ray shielding properties of the fabricated composites was evaluated using the Monte Carlo simulation and confirmed using the experimental measurements. The recorded results show an enhancement in the synthesized composites’ linear attenuation coefficient from 0.091 cm−1 to 0.106 cm−1 at a gamma ray energy of 0.662 MeV. Moreover, the excess in CaO concentration from 0 wt% and 60 wt% reduces the fabricated composites’ half-value thickness values from 7.64 cm to 6.51 cm, respectively.

Effect of zirconium oxide nanoparticles on thermal, optical, and radiation shielding properties of Bi2O3-B2O3-MnO2 glasses

This study has explored the DSC, UV–Vis absorption spectroscopy, gamma ray and neutron shielding properties of Bi2O3-B2O3-MnO2: ZrO2 glasses. It demonstrates a unique approach to photon shielding analysis using JENDL/PD-2016 photonuclear data and employs a validated spherical neutron model for neutron shielding. Five transparent glasses were prepared with the chemical composition (in mol%) of 29Bi2O3-70B2O3-(1-x)MnO2: xZrO2, and labeled as MZ0.00 (for x = 0), MZ0.25 (for x = 0.25), MZ0.50 (for x = 0.5), MZ0.75 (for x = 0.75) and MZ1.00 (for x = 1). The glass ceramic nature of the samples has been characterized by DTA thermograms. The glass forming ability parameters (Kgl, S & H) were found to be highest for the sample MZ1.00. The UV–Visible optical absorption spectra have been interpreted, and hence the cut-off wavelength (λcut-off) and optical band gap (Eo) were evaluated. The absorption spectra have revealed the co-existence of manganese ions in three stable valence states Mn4+, Mn3+ and Mn2+ in the samples. When ZrO2 nanoparticles were added in the composition up to x = 0.50 mol%, the red shift in the cut-off wavelength (λcut-off) with gradual shrinkage in optical band gap (Eo) has been observed. Also, the linear and non-linear optical parameters viz., refractive index (no), non-linear refractive index (n2), linear optical susceptibility (χ(1)) and non-linear optical susceptibility (χ(3)) have been evaluated. These parameters showcased that B-O, Bi-O, Mn-O, Zr-O, etc. bonds could be strengthened by subsequent reduction of polarization of the trivalent ions (B3+ ions, Bi3+ ions and Mn3+ ions) in the glass system at higher concentrations of ZrO2. Photoatomic and photonuclear attenuation studies portrayed that the sample MZ0.50 has the lowest photon shielding capability. The fast neutron effective removal cross section (ΣR) was observed to be the highest for the sample MZ1.00. Thus, these glasses can be used to design the thermally stable transparent glasses, tunable optical elements, and radiation shielding materials.

Enhancing mechanical, physical, radiation attenuation properties in alumino-barium-titanium-calcium-lithium glasses for nuclear applications: The pivotal role of TiO2additives

This study focused on enhancing key material properties of Alumino-Barium-Titanium-Calcium-Lithium glasses for nuclear applications, specifically by integrating increasing amounts of TiO2 additives. Utilizing the MCNPX general-purpose Monte Carlo code, version 2.7.0, the research aimed to ascertain Transmission Factor (TF) values across a spectrum of well-known radioisotope energies. This analysis was conducted for glass samples with varying thicknesses, ranging from 0.5 cm to 3 cm. The study also delved into the gamma-ray shielding characteristics of these glasses at energy levels between 0.015 and 15 MeV, uncovering notable findings. In exploring the T1 to T12 glass system, various physical and optical methods were employed to measure key parameters like glass density (ρglass), molar volume (Vm), oxygen molar volume (OMV), and oxygen packing density (OPD). A significant outcome of this research was the observation that with an increase in TiO2 content, there was a corresponding rise in glass density, from 3.727 g/cm3 to 3.825 g/cm3. Furthermore, the study noted alterations in the physical and mechanical properties of the glasses. Most notably, the T12 glass sample, which contained the highest concentration of TiO2, exhibited superior gamma-ray shielding properties compared to the other glass compositions analysed.

Impacts of siltstone rocks on the ordinary concrete's physical, mechanical and gamma-ray shielding properties: An experimental examination

A series of ordinary concrete is casted in order to examine the influence of the manganiferous siltstone rocks on the physical, mechanical, and gamma-ray shielding properties. Thus, a partial replacement for the coarse aggregates by siltstone rocks was performed during the fabrication of the currently ordinary concrete. The test revealed that raising the siltstone concentration improved the mechanical characteristics and density of the developed concretes. The addition of siltstone rocks at concentrations ranging from 0 to 40 wt% of the coarse aggregate concentration raises the density of the concrete from 2.05 g/cm3 to 2.3 g/cm3. Furthermore, partial substitution of basalt with siltstone rocks improves gamma-ray shielding properties. The experimental results for the linear attenuation coefficient show an increase in its value from 0.146 cm1 to 0.160 cm−1 when the siltstone concentration is increased between 0 and 40 wt% at 0.662 MeV. Furthermore, increasing the concentrations of siltstone affected the half-value thickness, which varied between 4.759 and 4.319 cm at 0.662 MeV. Therefore, the replacement presents a new alternative coarse aggregate that can enhance the mechanical and radiation shielding properties of ordinary concretes.

Structural, mechanical, optical, and radiation shielding properties for borotellurite glasses

In this work, six glass samples previously fabricated were used to prepare three glass systems by the melt-quench technique. X-ray diffraction and Fourier transform infrared studied the structure of refabricated glasses. At the same time, the Makishima–Mackenzie model was used to assess the elastic moduli for refabricated glasses. The optical properties of refabricated glasses were calculated based on UV–Vis absorption. The radiation shielding features were evaluated based on the Phy-X and SRIM programs. The X-ray diffraction results exhibited the amorphous behavior for all refabricated glasses, while the Fourier transform infrared revealed several bands related to TeO2 and B2O3. The band gap values for TBBBSr, TBBBZn, and TBBBCd glasses are 3.439, 3.236, and 3.195 eV, respectively. The Young modulus values are 59.368, 57.843, and 56.358 GPa for TBBBSr, TBBBZn, and TBBBCd glasses, which indicate superior the TBBBSr glass sample on other glasses in mechanical properties. The mechanical, optical, and Fourier transform infrared results showed high compatibility. In contrast, the TBBBCd glass recorded the highest density and gamma-ray shielding properties; for example, the linear attenuation coefficient values at 15 MeV are 0.222 cm−1 for TBBBCd, 0.214 cm−1 for TBBBZn, and 0.188 cm−1 for TBBBSr. While, the TBBBZn glass showed the highest neutron shielding feature; for example, the fast neutron removal cross section is 0.088, 0.091, and 0.092 cm−1 for TBBBSr, TBBBZn, and TBBBCd, respectively. On the other hand, the TBBBSr displayed the highest shielding features for charged particles. In conclusion, the TBBBSr glass can be nominated for radiation shielding applications based on its superior mechanical properties and ability to stop charged particles.