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Abstract Aiming to extend the scope of utilizing glass in radiation shielding, this work investigates the radiation interaction response of a borate-based glass system. Four borate-glass samples of different substituting concentrations of calcium oxide ( $$70-x$$ 70 - x )B2O3: $$10$$ 10 Na2O $$:5$$ : 5 Al2O3 $$:15$$ : 15 BaO: $$x$$ x CaO were prepared. To assess the shielding performance of the prepared glass samples, a high-purity germanium detector and different radioactive sources (different energies) were used. Via the narrow beam method, the linear attenuation coefficients (LACs) were experimentally measured. So, the transmission factor (TF), the half-value layer (HVL), the tenth value layer (TVL), the mean free path (MFP), and the radiation protection efficiency (RPE) were calculated for all prepared samples. It was observed that the increase of the concentration of calcium oxide in the proposed borate-based glass samples leads to improve their performance in shielding against radiation. At low energy, the RPE of the samples is almost 100%. However, it was observed that as energy of the radiation source increases, the shielding performance of the samples will decrease. High energy dependence was found when calculating TF, HVL, TVL, and MFP. They were increased with the increase of the energy of the incident photons. At 0.662 MeV, the TF values are equal to 79.26, 79.00, 79.72, and 78.43% for BNABC-1, BNABC-2, BNABC-3, and BNABC-4 in the same oder, respectively. The application of the proposed composition of borate-based glass as a transparent shield against low-energy ionizing radiation was highlighted.

Aiming to extend the scope of utilizing glass in radiation shielding, this work investigates the radiation interaction response of a borate-based glass system. Four borate-glass samples of different substituting concentrations of calcium oxide ( 70 - x )B2O3: 10 Na2O : 5 Al2O3 : 15 BaO: x CaO were prepared. To assess the shielding performance of the prepared glass samples, a high-purity germanium detector and different radioactive sources (different energies) were used. Via the narrow beam method, the linear attenuation coefficients (LACs) were experimentally measured. So, the transmission factor (TF), the half-value layer (HVL), the tenth value layer (TVL), the mean free path (MFP), and the radiation protection efficiency (RPE) were calculated for all prepared samples. It was observed that the increase of the concentration of calcium oxide in the proposed borate-based glass samples leads to improve their performance in shielding against radiation. At low energy, the RPE of the samples is almost 100%. However, it was observed that as energy of the radiation source increases, the shielding performance of the samples will decrease. High energy dependence was found when calculating TF, HVL, TVL, and MFP. They were increased with the increase of the energy of the incident photons. At 0.662 MeV, the TF values are equal to 79.26, 79.00, 79.72, and 78.43% for BNABC-1, BNABC-2, BNABC-3, and BNABC-4 in the same oder, respectively. The application of the proposed composition of borate-based glass as a transparent shield against low-energy ionizing radiation was highlighted. [ABSTRACT FROM AUTHOR]

We report the mechanical properties, elastic moduli, and gamma ray attenuation properties of some TeO2–WO3–GdF3 glasses. Using the chemical composition of the selected glasses, the dissociation energy per unit volume (G t) and the packing density (V t) were calculated. Using the G t and V t values, Young’s, Shear, Bulk, Longitudinal Modulus, and Poisson’s ratio of the glasses are calculated. Next several fundamental gamma ray attenuation properties such as linear and mass attenuation coefficients, half value layer, mean free path, effective atomic number, effective electron density, effective conductivity, exposure, and energy absorption buildup factors are calculated in 0.015–15 MeV energy range. As a consequence of WO3–GdF3 substitution, the glass densities are observed in different values. The overall gamma ray attenuation properties are found to be enhanced through WO3 addition. Moreover, the increasing WO3 incorporation into glass configuration decreases the overall elastic moduli of glasses. It can be concluded that increasing WO3 may be a useful tool for enhancing the gamma ray attenuation qualities and decreasing the elastic moduli of TeO2–WO3–GdF3 in situations where a material with versatile mechanical properties is required.

This study investigates the effect of substituting tungsten(vi) oxide/gadolinium(iii) fluoride in tellurite glasses whose densities varies from 5.0879 to 5.3246 g/cm3 on gamma-ray absorption properties. A range of fundamental absorption parameters, including attenuation coefficients, half-value layer thicknesses, effective atom and electron numbers, effective conductivity, exposure, and energy absorption buildup factors, were studied for five different glass samples with varying substitution ratios. The ratio of tungsten(vi) oxide to gadolinium(iii) fluoride varied between 0 and 20 mol%, as well as the TeO2 ratio in the composition was maintained between 90 and 80 mol%. The sample with the composition of 80–20 mol% TeO2/WO3, which attained the maximum density value with 20 mol% WO3 addition, showed the highest gamma-absorption capabilities based on the obtained findings in the range of 0.015–15 MeV. In consideration of the mechanical and physical properties of WO3 in tellurite glasses, it can be concluded that WO3 incorporation is a crucial monotonic process that may be utilized to further improve the properties of glass shields.

We report the role of the chemical modifications on various gamma-ray attenuation properties of four different tellurite glasses reinforced through WO3. The chemical compositions and glass densities are used in terms of determining some critical attenuation properties, such as linear and mass attenuation coefficients, half value layer, and effective atomic number values. Based on the rise in density, it was determined that the maximum concentration of WO3 also resulted in a significant change in the overall gamma-ray absorption properties, when all of the study’s findings were examined. It was observed that the glass sample, in which TeO2 and WO3 were 40 mol%, had the highest density. It was found that this glass with the highest density has the highest linear attenuation coefficient and mass attenuation coefficient and the lowest half value layer among the four samples specified. This demonstrates that WO3 inclusion is a functional component that may be used in tellurium glasses and is a suitable material for situations requiring increased gamma-ray absorption properties.

We report the physical, optical and nuclear radiation attenuation behaviours of tellurite–germanate (TeO 2 –GeO 2 –PbO) glasses reinforced with varying amounts of Eu 2 O 3. The samples were synthesised using the conventional melt-quenching method and had the following composition (in wt.%): 33.34TeO2 - 33.33GeO 2 - 33.33PbO (TGP). Different concentrations of Eu2O3 (in wt.%) were added to the glass composition, labelled TGP1, TGP2 and TGP3. The physical, optical and nuclear radiation attenuation properties were measured using both experimental and theoretical methods. At room temperature, the visible to near-infrared optical absorption spectrum ranged from 400 to 900 nm. The TGP1 sample with 1 wt% The Eu2O3 additive exhibited the lowest absorbance and the highest transparency. The TGP1 sample also exhibited the highest nuclear radiation absorption properties. The gamma-ray absorption capabilities of TGP1 were demonstrably superior to those of various types of glass shields and other old- and new-generation concrete-shielding materials. Thus, adding 1 wt% Eu 2 O 3 to tellurite–germanate glasses would 'improve nuclear radiation absorption and optical properties. It can also be concluded that expanded scientific community investigations in this area would be a significant step toward gaining a deeper understanding of these glass structures and determining what other optimisation tasks the addition of 1 wt% Eu 2 O 3 can accomplish. [ABSTRACT FROM AUTHOR]

This study aimed to investigate the nuclear radiation shielding properties of erbium (Er)-reinforced and samarium (Sm)-reinforced borate glasses. In the 0.015–15 MeV photon energy range, attenuation coefficients, as well as half-value layer tenth-value layers, and the mean-free path have been calculated. Additionally, effective, and equivalent atomic numbers, effective atomic weight, electron density, and exposure and energy absorption build-up factors were also calculated. To evaluate the overall nuclear radiation attenuation competencies of Er-rich and Sm-rich glasses, effective removal cross-section values for fast neutrons and projected range/mass stopping power values for alpha and proton particles were also determined. The glass sample BZBEr2.0 had the highest linear and mass attenuation coefficients (µ and µ m), effective conductivity (C eff), the effective number of electrons (N eff), and effective atomic number (Z eff) values as well as the lowest half-value layer (T 1/2), tenth value layers (T 1/10), mean free path (λ), exposure build-up factor, and energy absorption build-up factor values. µ m values were reported as 2.337, 2.556, 2.770, 2.976, 2.108, 2.266, 2.421, 2.569, and 2.714 for BZBEr0.5, BZBEr1.0, BZBEr1.5, BZBEr2.0, BZBSm0.0, BZBSm0.5, BZBSm1.0, BZBSm1.5, and BZBSm2.0 glass samples at 0.06 MeV, respectively. The results showed that Er has a greater effect than Sm regarding the gamma-ray shielding properties of borate glasses. The results of this investigation could be used in further investigations and added to older investigations with the same aim, to aid the scientific community in determining the most appropriate rare-earth additive, to provide adequate shielding properties based on the requirement.

Tellurite glasses are known to present attributes which makes them attractive for optical and radiation shielding functions. This study presents the optical and γ-radiation absorption quantities of (89-x)TeO 2 - x ZnCl-10ZnO-Yb 2 O 3 (for 0 ≤ x ≤ 30 mol. % in steps of 10 mol. % and coded as TZZCY1-TZZCY4 accordingly). The optical characteristics of the glasses were determined through the estimation and analysis of optical quantities such as the molar volume, molar refractivity, molar polarizability, reflection-loss, optical-transmission, metallization-criterion, static dielectric constant and the optical dielectric constant. The mass attenuation coefficient MAC of the glasses was estimated for energy E in the range 0.015 ≤ E ≤ 15 MeV through XCOM computation and photon transmission simulation by PHITS. The gamma ray shielding competence of the glasses was analysed through the computed mass attenuation coefficient, the linear attenuation coefficient, effective atomic number, mean free path, and half-value layer HVL. The molar refractivity, molar polarizability, reflection loss, static dielectric constant, and optical dielectric constant, all decline with increase in ZnCl 2 content of the glasses while the optical transmission and metallization criterion increases. The addition and increase in the proportion of ZnCl 2 compromised the photon-absorption ability of the TZZCY glasses although the optical transparency of the glasses was improved. [ABSTRACT FROM AUTHOR]

We present a comprehensive study on the transformation of municipal slug wastes into glass samples with exceptional gamma-ray attenuation capabilities that may be used in medical and industrial radiation applications to the benefit of society. The whole process is performed using an adsorbent developed by loading iron oxide and TiO 2 on municipal solid waste melted slag. The loading is carried out through chemical reactions and high-temperature process. The oxidation of arsenite with a concentration of 100 mg L−1 is completed in 3 h. Next, the glass synthesis process is performed using well-known melt-quenching method. Structural, optical, and gamma-ray attenuation properties are determined using experimental and theoretical methods. Our findings showed that a wide hump centered at 2θ= 30° with no indication of any precise peaks emerging in the crystalline phases and glasses under investigation have amorphous natures. Using several well-known radioisotope energies, the half-value layers of slow waste glasses are determined. The 11-G sample demonstrated the greatest gamma-ray attenuation characteristics among the manufactured glass samples. The 11-G sample's half layer values are then compared to those of comparable glass, concrete, and polymer shields available in the literature. The results demonstrated that 11-G is clearly better than the other shield types. It can be concluded that some other novel materials with superior shielding properties may be manufactured using more thoroughly separating techniques in terms of determining the best conditions for this type of superior materials. It can be also concluded that some other characterization phases may be conducted in terms of identifying the undiscovered properties of the current samples towards better understanding of slug-waste based glasses and their potential applications. • A transformation process of municipal slug wastes into glass samples is conducted. • Ten different slug waste powders are recycled to ten novel glasses. • Structural, optical, and gamma-ray attenuation properties are determined. • Half layer values are compared to glass, concrete, and polymer shields. • 11-G sample is reported with superior properties. [ABSTRACT FROM AUTHOR]