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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 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]

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]