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The efficiency of geopolymers as an effective immobilization system for various hazardous waste materials can be enhanced by adding PbO to improve its radiation shielding characteristics. In this study, the impact of PbO addition on the shielding properties of geopolymer composites was examined to evaluate the gamma radiation shielding characteristics of the geopolymer using FLUKA and XCOM computer programs. The results showed that adding 10% and 20% lead oxide significantly improved the shielding properties of the investigated geopolymer, mostly at lower photon energies. The higher values of MAC of 59.66728 cm2/g at 0.015 MeV, and 0.03916 cm2/g at 15 MeV for the investigated geopolymers suggest that these materials have improved radiation shielding at lower and intermediate energies due to higher photoelectric absorption and Compton scattering. The findings of this study provided valuable insights for designing high-performance radiation protection in medical imaging facilities, nuclear power plants, industrial radiography and other special radiation installations. Therefore, GEO doped with 20PbO should be deployed to fortify these facilities against ionizing radiations. [ABSTRACT FROM AUTHOR]

Gamma‐ray, fast neutron and charged particle shielding characteristics of Praseodymium (Pr3+) activated glasses with composition 10ZnF2‐(10‐x)SrO‐15Li2O‐65H3BO3‐xPr2O3(where x = 0.1, 0.5, 1.0, 1.5, and 2.0) are investigated. For this, the radiation shielding parameters are estimated by using Photon Shielding and Dosimetry (Phy‐X/PSD), Interaction of Proton, Alpha, Gamma rays, Electrons, and X‐rays with matter (PAGEX), Stopping Powers and Ranges for Electrons (ESTAR), and The Stopping and Range of Ions in Matter (SRIM) codes. Furthermore, the results are compared comprehensively and comparatively. The glasses with increasing Pr3+ content exhibited higher shielding potential. It can be said that the ZFLHBPr2.0 sample could be used as a shielding material in various applied fields. Additionally, the effect of Pr composition on structural transitions and time‐dependent volume‐collapse of this new family of borate glass doped with Pr is analyzed by molecular dynamics study (MD) based density functional tight binding method. The simulation results show that the addition of Pr led to the cubic‐orthorhombic transformation of simulation cell at determined temperature and 1 atm pressure. Also, a sudden decrease in volume are observed within a short time at 8% Pr composition (x = 2.0) atmospheric pressure. This result provides a strong connection between Pr composition and volume change with time and at constant low pressure. [ABSTRACT FROM AUTHOR]

The structural, mechanical and radiation shielding properties of (69-x)B 2 O 3 -20TeO 2 -10Al 2 O 3 -1HfO 2 -xPr 6 O 11 (where x = 0, 0.25, 0.5, 0.75, 1 mol %) glass system were investigated. This study introduces a novel approach by incorporating Pr 6 O 11 into glass composition, highlighting its unique contributions to enhancing elastic properties, fracture toughness, hardness, and radiation shielding abilities. Experimental measurements were conducted within the energy range of 59.54–661.62 keV and theoretical calculations are made for MAC values. The presence of Pr 6 O 11 was noted to positively influence the gamma shielding capabilities. At 59.54 keV, the addition of 0.25 mol% Pr 6 O 11 increased the mass attenuation coefficient of the glass by 2.9 %, and the addition of 1 mol% Pr 6 O 11 increased it by 29.8 %. The addition of 0.25 mol% Pr 6 O 11 increased the fast neutron removal cross section of the glass by 4.4 %. Also, it is observed that the glass with 1 mol% Pr 6 O 11 is the best shielding material against alpha and proton particles. A significant enhancement of 24.36 % in the fracture toughness value was observed, increasing from 1.059 to 1.317 MPa m1/2 at 1 mol% Pr 6 O 11. Experimental hardness values increased from 3.374 to 3.985 GPa, resulting in an improvement of 18.11 % at 1 mol% Pr 6 O 11. The thermal stability (ΔT, °C) value demonstrated a notable increase from 85 to 106, indicating a significant 24.7 % improvement at 0.25 mol% Pr 6 O 11. [ABSTRACT FROM AUTHOR]

Abstract The efficiency of geopolymers as an effective immobilization system for various hazardous waste materials can be enhanced by adding PbO to improve its radiation shielding characteristics. In this study, the impact of PbO addition on the shielding properties of geopolymer composites was examined to evaluate the gamma radiation shielding characteristics of the geopolymer using FLUKA and XCOM computer programs. The results showed that adding 10% and 20% lead oxide significantly improved the shielding properties of the investigated geopolymer, mostly at lower photon energies. The higher values of MAC of 59.66728 cm2/g at 0.015 MeV, and 0.03916 cm2/g at 15 MeV for the investigated geopolymers suggest that these materials have improved radiation shielding at lower and intermediate energies due to higher photoelectric absorption and Compton scattering. The findings of this study provided valuable insights for designing high-performance radiation protection in medical imaging facilities, nuclear power plants, industrial radiography and other special radiation installations. Therefore, GEO doped with 20PbO should be deployed to fortify these facilities against ionizing radiations.

As the nuclear industry has developed and radiation technologies have become more widely used, the dose of radiation from both synthetically produced sources and radioisotopes has increased, as has the number of people being irradiated. It is of the utmost importance to utilise appropriate shielding materials in order to reduce the negative effects of radiation sources. Doped glasses are among the most significant candidate materials in the field of radiation shielding. To this end, it was aimed to investigate the charged particle, gamma-ray and neutron shielding characteristics of ytterbium doped glasses with composition of 50Bi2O3-15Li2O-15PbO-(20-x)B2O3-Yb2O3 (where x = 0.5, 1.0, 1.5, 2.0 and 2.5). In this regard, the radiation shielding parameters were estimated by using Phy-X/PSD, PAGEX, ESTAR, and SRIM codes. Furthermore, the results were compared comprehensively and comparatively. Charged particle (alpha, proton and electron), gamma ray and neutron shielding efficiencies were found to be proportional to ytterbium content. The glasses with the increasing amount of ytterbium exhibited higher shielding performances. It can be said that all the studied glasses and particularly Yb2.5 sample could be used as shielding materials in many radiation related applications. [ABSTRACT FROM AUTHOR]

This study examined the suitability of several glass compositions as a gamma-ray shielding substance. The compositions tested were of varying ZnO concentrations, specifically (60-x) B2O3—10Na2O—15SiO2—5Al2O3—(x + 10)ZnO (where X = 5, 10, 15 and 20 mol%). Measurements were performed at energy levels of 0.6642, 1.1776, and 1.3343 MeV radiated from Cs137 and Co60 point sources along with a scintillation detector [NaI(TL)]. We investigated the critical properties related to gamma radiation shielding, determining the effective atomic number (Zeff), electron density (Nel), half-value layer (HVL), linear attenuation (μ) and mass attenuation (μm) coefficients, and mean free path (λ). Our results show that the glasses under examination get denser (from 2.12 to 2.77 g/cm3) as the Zn concentration rises from 15 to 35 mol %. In addition, all glass compositions provide adequate protection against gamma radiation at the specified energy levels. The values of µ went up from 0.157 to 0.214 cm−1 (0.6642 MeV), from 0.119 to 0.160 cm−1 (1.1776 MeV), and from 0.114 to 0.151 (1.3343 MeV). For samples B1 and B4, the observed HVL values dropped from 4.41, 5.84, and 6.12 cm to 3.21, 4.31, and 4.61 cm at 0.6642, 1.1736, and 1.3343 MeV, respectively. Among the materials tested, prepared glasses show higher shielding capacity compared to regularly used glass and concrete samples. The study highlights these glass compositions' potential as practical materials that can shield gamma radiation. [ABSTRACT FROM AUTHOR]

The density, boron–boron separation, and molar volume of 4Al2O3–12Na2O-(18-x)SiO2-(64-x) B2O3-(2+2x)Bi2O3 (where x = 2, 4, 6 and 8 mol%) are increasing with the addition of Bi2O3. The addition of Bi2O3 results in an open network structure. The elastic moduli decrease from 34.711 to 29.875 GPa for Young modulus (E); 20.395 to 15.843 GPa for bulk modulus (B); from 15.257 to 13.494 GPa for shear modulus (G) and 40.738 to 33.836 GPa for longitudinal (L) respectively with increased Bi2O3 concentration. FTIR spectrainvestigation found BO3, BO4, SiO4, and BiO6 structural units to be present. The glasses' highest mass attenuation coefficient (MAC) is at 0.0395 MeV, the lowest energy value. It gradually decreases as energy increases. There is a decrease in the linear attenuation coefficient (LAC) values with energy. Sample Bi18 has the highest MAC and LAC values due to its high concentration of Bi2O3. Across the entire energy range, sample Bi18 has the highest effective atomic number, and the lowest half value layer and mean free path values across all energy values. The transmission factor (TF) values for Bi6 indicate that the required thickness for blocking 90% of the radiation must be greater than the thickness necessaryfor the attenuation of 50%. Bi18 has the lowest TF compared to other glass samples. The radiation protection efficiency values for Bi18 are highest, confirming their full protection ability. Bi18's is the best choice for radiation shielding.

High-entropy materials are one of the most studied topics in recent years due to the extraordinary properties they exhibit. High entropy oxide (HEO) is a group of materials that have been studied for different applications. However, the effects of HEOs on the radiation properties of glasses are not well known. In this study, the structural, radiation and neutron shielding properties of SiO 2 glass systems doped erbium oxide reinforced with refractory high entropy oxide (RHEO) with the formula TiMoNbTaWZrO 11 were investigated. RHEAs used in the study were produced and characterized in our laboratory. Then, they were added to the glass samples at different rates together with Erbium oxide. As a result of SEM-EDS and XRD analyses, it was determined that the additives were distributed very homogeneously on the glass. The composition of glass systems is [95SiO 2 +(5-x)Er 2 O 3 +x TiMoNbTaWZrO 11 ], where (x = 0, 0.5, 1 and 2 %, mol). The linear and mass attenuation coefficients (LAC and MAC), mean free path (MFP), half-value layer (HVL) and effective atomic numbers (Z eff) and effective electron density (N el) of the glass structures were experimentally measured at the energy region of 53.16–661.62 keV. Also, the equivalent dose rates due to fast neutrons absorption were measured by using an 241Am–Be fast neutron source. Exposure buildup factor (EBF) and fast neutron removal cross section (ΣR) were theoretically determined. The proton and alpha shielding parameters of glasses were calculated. It is observed that glasses containing higher amounts of refractory high entropy oxide, within the SiO 2 –Er 2 O 3 composition, demonstrated enhanced capabilities for shielding against radiation and neutrons. [ABSTRACT FROM AUTHOR]

As a "green" radiation protection material with the potential to replace lead oxide, bismuth oxide has more research applications in the field of γ protection. However, due to their different surface properties, there are compatibility and interaction problems between metal oxides and rubber. To enhance the performance of bismuth oxide in neoprene, Bi2O3@PCPA‐KH590 was prepared by coating bismuth oxide with polyphenol/polyamine and grafting KH590 on the surface of bismuth oxide. This allows for creating more active sites with the help of polyphenol/polyamine, enabling KH590 to be grafted onto bismuth oxide particles. The S functional group on the silane coupling agent is then cross‐linked with the rubber substrate, enhancing the dispersibility of the bismuth oxide powder. This improvement not only improves the dispersibility of the bismuth oxide powder but also enhances the mechanical properties of the rubber composite material. Compared with pure CR, the mechanical properties of 60 wt% filler‐modified powder composites can still be maintained at a high level, with the tensile strength reaching 12.83 Mpa. In sum, the proposed method appears feasible for preparing highly filled radiation protection rubber‐based materials. [ABSTRACT FROM AUTHOR]

In various medical, industrial, and nuclear facilities, it is very necessary to have enough shielding against the radiation released by regularly employed isotopes. In this work, we concentrate on nuclear security as well as the radiation shielding against gamma attenuation capabilities of the borate glasses, including Te and Cu. These glasses have the chemical form of (100-x)[30B2O3–70TeO2]-xCuO, where x = 0, 0.005, 0.01, 0.015, 0.02 wt%. The systems were represented by five distinct samples, labelled as BTCu-20, BTCu-15, BTCu-10, BTCu-5, and BTCu-0, where the number refers to the percentage of CuO in the mixture and the remainder is made up of TeO2 and B2O3. Through the use of FLUKA simulations, the basic characteristics associated with gamma shieldings, such as attenuation and transmission factors, were examined for the particular energy range of 238–1408 MeV emitted from 133Ba, 137Cs, 60Co, 152Eu, and 232Th. The effect of the systematic replacement of CuO by B2O3 and TeO2 on the shielding qualities was explored in depth for gamma radiation. In addition, comparison research was carried out between the currently available borate glasses and the traditional shielding materials. According to the findings of the current investigation, the GHVL was found to be its lowest at 238 keV with values of 0.87, 0.92, 0.98, 1.04, and 1.10 (cm) for BTCu-0, BTCu-5, BTCu-10, BTCu-15, and BTCu-20 glasses, respectively. This points to the possibility that the BTCu-0 sample might be used in radiation shielding applications, which would result in increased nuclear safety.

In this study, a PbO, MnO2, PbO + MnO2 thin film (nano layer) was deposited onto a microscope glass, indium tin oxide glass, and aluminum with thicknesses 0.1 mm and 0.5 mm substrate, samples were prepared by the thermal spray technique. The coating of thin films was carried out onto the substrate at a temperature of 35 °C, furthermore, the prepared shield films were annealed at 100 °C and 250 °C for one hour. The shielding efficiency of each thin film on each substrate at different temperatures was analyzed using radioactive source 60Co and NaI(Tl) well-type scintillation detector. The experimental results obtained were summarized: adding PbO or MnO2 thin film together or separately to the substrate increases the attenuation of gamma-rays depending on the type of samples and annealed temperature. The minimum gamma reduction rate was found 0.3 % for indium tin oxide glass deposited with MnO2 and annealed at 250 °C while the maximum was found in Al with thickness 0.1 mm (9.6 %) deposited with both PbO or MnO2 together. This means that shielding efficiency increases by increasing the thickness of the thin film, annealed temperature and substrate type. [ABSTRACT FROM AUTHOR]

The gamma, neutron and charged particle shielding behaviour of TaC, WC, HgO, PbO and Bi2O3 doped PVA polymers were studied. The gamma and neutron shielding parameters were calculated using EpiXS and NGCal software. Also, (stopping power and range) charged particles such as electrons, protons, alpha and carbon ions were calculated using the ESTAR and SRIM programmes. The increase in weight percent of TaC in PVA polymer increases the value of mass attenuation coefficient, and decreases the mean free path. Similar results were observed for WC, HgO, PbO and Bi2O3-doped PVA polymers. At 0.662 MeV, the mass attenuation coefficient of 50PVA+50TaC is 0.08960 cm2/g, 50PVA+50WC is 0.0902 cm2/g, 50PVA+50HgO is 0.0944 cm2/g, 50PVA+50PbO is 0.0958 cm2/g, and 50PVA+50Bi2O3 is 0.0964 cm2/g. The 50 wt% of Bi2O3 doped PVA shows a 35% enhancement in the values of mass attenuation coefficient and a 25% reduction of mean free path up to 100 keV in contrast to the 50 wt% of TaC doped PVA. It was discovered that 50 wt% of Bi2O3 doped PVA outperforms 50 wt% of TaC doped PVA, and these selected polymers are lighter than commercial shields. Therefore, 50 wt% of Bi2O3 doped PVA is a good gamma, neutron, and charged particles shielding material. [ABSTRACT FROM AUTHOR]

In this study, a PbO, MnO2, PbO + MnO2 thin film (nano layer) was deposited onto a microscope glass, indium tin oxide glass, and aluminum with thicknesses 0.1 mm and 0.5 mm substrate, samples were prepared by the thermal spray technique. The coating of thin films was carried out onto the substrate at a temperature of 35°C, furthermore, the prepared shield films were annealed at 100°C and 250°C for one hour. The shielding efficiency of each thin film on each substrate at different temperatures was analyzed using radioactive source 60Co and NaI(Tl) well-type scintillation detector. The experimental results obtained were summarized: adding PbO or MnO2 thin film together or separately to the substrate increases the attenuation of gamma-rays depending on the type of samples and annealed temperature. The minimum gamma reduction rate was found 0.3 % for indium tin oxide glass deposited with MnO2 and annealed at 250°C while the maximum was found in Al with thickness 0.1 mm (9.6 %) deposited with both PbO or MnO 2 together. This means that shielding efficiency increases by increasing the thickness of the thin film, annealed temperature and substrate type.

This research entailed the production of composite materials through the combination of natural rubber and acrylonitrile butadiene rubber, along with nano-silica-loaded bismuth (III) oxide, in varying concentrations ranging from 0 to 45 parts per hundred parts of rubber (phr). The gamma attenuation properties of the composites at different concentrations of Bi2O3 were measured. Additionally, the mechanical properties of the resulting composites, including hardness, tensile strength, and elongation, were tested. The composites with a concentration of 20 phr exhibited the highest tensile strength and elongation at break, followed by a subsequent decrease as the concentration of Bi2O3 increased. The gamma mass-attenuation coefficient of the composites increased as the Bi2O3 concentration increased from 0 to 45 phr, with values ranging from 0.083 to 0.090 cm2/g at 0.662 MeV. Moreover, the fast neutron mass removal cross-sections ranged from 0.092 to 0.072 cm2/g, corresponding to the variation of Bi2O3 concentration from 0–45 phr are also determined. Various parameters related to gamma-ray shielding, including the half-value layer, exposure build-up factor (EBF) up to 40 mean free path (mfp) penetration depth, and effective atomic number (Zeff) are also included. The radiation-induced aging of the prepared blend is tested by measuring the effect of radiation exposure on its shielding capability via its porosity change. The obtained results indicated that the prepared composites could be used for several radiation-protection applications. [ABSTRACT FROM AUTHOR]

Solar cells in superstrate arrangement need a protective cover glass as one of its main components. The effectiveness of these cells is determined by the cover glass's low weight, radiation resistance, optical clarity, and structural integrity. Damage to the cell covers brought on by exposure to UV irradiation and energetic radiation is thought to be the root cause of the ongoing issue of a reduction in the amount of electricity that can be generated by solar panels installed on spacecraft. Lead-free glasses made of xBi2O3–(40 − x)CaO-60P2O5 (x = 5, 10, 15, 20, 25, and 30 mol%) were created using the usual approach of melting at a high temperature. The amorphous nature of the glass samples was confirmed using X-ray diffraction. At energies of 81, 238, 356, 662, 911, 1173, 1332, and 2614 keV, the impact of various chemical compositions on gamma shielding in a phospho-bismuth glass structure was measured. The evaluation of gamma shielding revealed that the results of the mass attenuation coefficient of glasses increase as the Bi2O3 content increases but decrease as the photon energy increases. As a result of the study conducted on the radiation-deflecting properties of ternary glass, a lead-free low-melting phosphate glass that exhibited outstanding overall performance was developed, and the optimal composition of a glass sample was identified. The 60P2O5–30Bi2O3–10CaO glass combination is a viable option for use in radiation shielding that does not include lead. [ABSTRACT FROM AUTHOR]

Multifunctional radiation shielding materials are important for the development of miniaturised nuclear reactors. Bi6B10+2xO24+3x (x = − 2, − 1,0,1,2) compounds were economically and conveniently synthesised by using a solid-state sintering reaction of bismuth oxide and boric acid. The effects of liquid phase boron oxide migration due to sintering temperature and boric acid content on the microscopic morphology, crystalline phase composition and macroscopic properties of the samples were systematically investigated. And the studies highlight that when the content of boric acid particles increases, the nucleation and growth of bismuth borate is accelerated, which promotes the sintering of the ceramic and have a positive effect on improving the physical properties of materials. The ceramic with x = 1 exhibited the highest cold elastic modulus (28.41 GPa), cold flexural strength (18.55 MPa) and room temperature thermal conductivity (0.3420 W/(m·K)). Radiation shielding tests showed neutron and gamma shielding of 63.7% and 39% for the ceramic with x = 1 when the sample thickness was 1.5 cm. Thus, based on the information gathered from our research, Bi6B10+2xO24+3x (x = − 2, − 1,0,1,2) ceramics were expected to be designed as an integrated nuclear reactor shielding/insulation material. [ABSTRACT FROM AUTHOR]

A series of phosphate glass with the following formulation was manufactured using the melt quenching procedure: 3As2O3 - 37PbO -- (60 -x) P2O5- x WO3, x = (0 ≤ x ≤ 5 mol. %). The glasses' physical and other structural characteristics were examined in depth. The basic structural properties of the materials were examined using a variety of characterization procedures, such as XRD and FT-IR. With increasing WO3 concentration, the phosphate network evolves, leading to depolymerization of the glass network, according to the FT-IR analysis. With increasing WO3, the physical, mechanical, and structural parameters were enhanced like glass density, longitudinal and shear speeds, and all elastic moduli. Because of P--O--W bonds in the glass network are stronger than P--O--P bonds, the radiation characteristics were enhanced as the content of WO3 increased. The interpretation of the parameters showed that the glass in the statement is an excellent candidate for photon shielding applications. [ABSTRACT FROM AUTHOR]

In this work, black nanocarbon-loaded 0–100 parts-per-hundred (phr) PbO-filled acrylonitrile butadiene rubber (NBR)/styrene-butadiene rubber (SBR) blend composites were prepared by using an ordinary standard rubber mixer. Both mechanical and gamma attenuation properties of the prepared samples were investigated. Maximum tensile strength and elongation at break were obtained at 40 phr PbO concentration. The obtained values for the mass attenuation coefficient with the increased PbO concentration from 0–100 phr ranged from 0.12–0.22 cm2/g at 0.239 MeV. Scanning electron microscope (SEM) with the elemental mapping analysis results showed high homogeneity at 40 phr of the prepared rubber composites, with some areas of elemental agglomeration at a high concentration of lead oxide. The obtained results highly recommend the use of the prepared nanocarbon-reinforced PbO/NBR/SBR blend compared to those previously used as personal protective equipment in radiation-shielding applications. [ABSTRACT FROM AUTHOR]

3D printer technology has recently become easily reachable technology and are used to create simple or complex structures with high-quality. Its superior advantages could also be useful on the production of effective radiation shielding materials. On this purpose, the presented work studies the gamma and neutron shielding effectiveness of Acrylonitrile Butadiene Styrene (ABS) sample, a 3D printing material, reinforced with Bi and TiO2 nanopowders at various gamma and neutron energies. The gamma shielding properties were evaluated using experimental (High Purity Germanium detector system), theoretical (WinXCOM computer program) and simulation techniques (GEANT4 and FLUKA) in a wide gamma energy region ranging from 59.5 to 1332.5 keV. The investigation on neutron attenuation capabilities of the printed composites were performed with help of simulation and theoretical approaches for various sample thickness and neutron energies. The half value layer of ABS-Bi10 sample is found to be as 4.9565 cm, which is much smaller than some commercial polymers: polyvinylidenechloride, polyamide, polyacrylonitrile, polyphenylenesulfide, and unsaturated polyester. With the usage of 3D printing technology, significant enhancements in neutron and gamma shielding were reported. [ABSTRACT FROM AUTHOR]

This article focuses on exploring the effects of CdO on the optical, radiation, and physical characteristics of sodium borophosphate glass with different compositions. The glass compositions included B 2 O 3 , Na 2 O, P 2 O 5 , and varying content of CdO from 0 to 12 mol %. One of the observed effects of adding CdO to the glass composition is a substantial increase in glass density. The density increased from 3.42 g/cm³ to 4.87 g/cm³ as the CdO increased. UV–visible spectroscopy was utilized to determine the optical bandgap and other correlated physical parameters. Bandgap values increased from 2.39 to 2.74 eV for E o p t i n d and from 2.51 to 2.82 eV for E o p t d i . Connections between the optical and physical characteristics of CdNaBP glasses are discussed. Moreover, different shielding parameters were assessed using Phy-X simulation software. This study explores the importance of radiation shielding efficiency and the positive impact of higher CdO content on photon blocking in sodium borophosphate glasses. The addition of CdO enhances the radiation shielding capabilities of this glass. Additionally, the study explored the gamma shielding properties. Hence, all these observations infer that the CdNaBP-12 glass sample is the most suitable for transparent radiation shielding applications. • This article focuses on exploring the effects of CdO on sodium borophosphate glass. • The density increased from 3.42 g/cm³ to 4.87 g/cm³ as the CdO increased. • The values band gap shifted from 2.39 to 2.74 eV for E o p t i n d and from 2.51 to 2.82 eV for E o p t d i . • The glass sample CdNaBP −12 exhibited the best properties. [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.

Tungsten is a metal with high density, durable, good in terms of hardness and strength compared to lead. In this study, gamma shielding parameters such as mass attenuation coefficient, linear attenuation coefficient, half value layer, tenth value layer, mean free path, effective atomic number and effective atomic density for some tungsten-containing minerals (tungstibite, tungstenite, hubrenite, russellite, anthoinite) in the energy range of 0.060 MeV to 2.614 MeV were investigated with the help of WinXCOM program, GEANT4 and FLUKA simulation codes and the obtained results were compared with each other. It has been observed that tungstenite may be a better gamma shielding material around the K shell absorption edge energy (0.0695 MeV) of tungsten, while russellite may be a better gamma shielding material in other energy regions. [ABSTRACT FROM AUTHOR]

Various samples were fabricated and characterized in the system 61B2O3 – 19SiO2- (20 - x) MoO3 - x CeO2, x = (0 ≤ x ≤ 12 mol%). The procedure of XRD was used to determine the status of the samples. FT-IR shows the network of octahedral [MoO6], in addition to [SiO4], [BO3], and [BO4] structural units. The conversion of BO3 units to BO4 groups consumes the modifier component of CeO2. The remaining CeO2 can connect to the network as CeO4 units. To determine the elastic characteristics of glasses, ultrasonic velocities were measured. Ultrasonic velocities and elastic moduli increased as CeO2 concentrations increased. The results were compared using theoretical considerations after the elastic moduli were evaluated experimentally. Radiation shielding occurrence appears to be solely a function of CeO2 concentration, according to glass radiation shielding investigations. The MAC values are clearly increasing as CeO2 rise, and the samples are in ascending order (MBSCe12) >(MBSCe10) > (MBSCe8) > (MBSCe4) > (MBSCe2) > (MBSCe0). The value of (FRC) rises steadily as the CeO2 content rises. As a result, the glasses which have higher CeO2 content are better gamma-ray shields and absorbers. Significant radiation attenuation attributes were demonstrated when CeO2 reinforcement was used. [ABSTRACT FROM AUTHOR]

The rapid-quenching route was used to prepare Na2B4O7–CaO–SiO2 glass formulations with various Cr2O3 concentrations. XRD analyses were used to determine the amorphous states of glasses. With the addition of Cr2O3, the glass density increased while molar volume reduces. The elastic moduli and velocities have been discovered to be affected by Cr2O3 concentration. A theoretical model of the prepared glasses' gamma-ray shielding ability has also been developed. With increasing photon energy, the mass attenuation coefficient values were found to reduce. As a result, G 5 glass provides more shielding than other glasses. Incorporating Cr2O3 into the investigated glass compositions has a significant influence on their mechanical and gamma shielding features, according to the findings of this study. In the future, this research could be used to improve mechanical efficiency and reduce radiation's harmful effects on organisms. [ABSTRACT FROM AUTHOR]

This research aims to investigate the structural and gamma shielding properties of different resin composite dental materials for medical applications. For this study, morphological structures and elemental compositions of the investigated composite samples were obtained by SEM/EDS analysis. The FTIR spectroscopy was employed to understand the bond structures of the resin composites. In addition to structural analyses, some of vital gamma radiation attenuation parameters were determined using MCNPX general purpose Monte Carlo code (version 2–6-0). The results showed that 3 M, GC, and Tokuyama composites indicated more regular and homogeneous structure. Zn, Zr, Ba, Sr, and Yb heavy elements were added in certain proportions in order to increase the radiopacity of the restorative material in the studied samples. As FTIR results were interpreted, C–O, O–H, and Si–O bonds were observed in all of the composites. Moreover, Bisco was found to be the most successful in reducing radiation intensity among the others, while Tokuyama was the least effective material to attenuate photon intensity. The elements Zn and Yb in Bisco have increased radiopacity and radiation absorption capabilities. It can be concluded that outcomes of the present investigation would be useful for ionizing radiation application in medicine especially in diagnostic imaging and radiation treatment. [ABSTRACT FROM AUTHOR]

In the radiation protection application, the metal-polymer composites have been developed for their radiation shielding properties. In this research, the elastomer composites doped by 10 μm and100nm size of lead, bismuth and tungsten particles as filler with 30 and 60 wt percentages were prepared. To survey the shielding properties of the polymer composites using gamma-ray emitted from 152Eu and 137Cs sources, the gamma flux was measured by using NaI(Tl) detector, then the linear attenuation coefficient was calculated. Also, the Monte Carlo simulation (MCs) method was used. The results showed a direct relationship between the linear attenuation coefficients of the absorbent and filler ratio. Also, the decrease in the particle size of the shielding material in each weight percentage improved the radiation shielding features. When the dimension of the particles was in the order of nano-size, more attenuation was achieved. At low energies used for medical diagnostic X-ray applications due to the predominance of the photoelectric effect, bismuth and lead were suitable selection as filler.

Zinc lead silicate glass system contains different amount of WO3 were fabricated using the classical melt-quench technique. The nature of the samples was investigated using X-ray diffraction. The ultrasonic velocities and elastic moduli were tested experimentally after that the results were compared by using the theoretical consideration. With increasing the WO3 content, decreasing the molar volume causes a decrease in the inter-ionic distance Ri. The FLUKA code were used to estimate the main attenuation considerations mass attenuation coefficients (MAC) and linear attenuation coefficients (LAC). The LAC increment from 0.728 cm-1 to 0.856 cm−1 as the WO3 concentration increment from 0 to 5 mol%, resulting in high shielding performance for G5. The dose rate at energy of 0.6 MeV with the G5 sample found to be declines from 2.35 × 107 R/h at 1 mm to 4.71 × 106 R/h at 4 mm. The values of mean free path (MFP) and the half value layer (HVL) are smaller than those of the traditional photon shields signifying that the fabricated samples (particularly G5) have interesting shielding characteristics to be used in applications involving x/gamma rays. [ABSTRACT FROM AUTHOR]

Experimental investigation requires materials, radiation sources, and test arrangements with a high monetary financial plan. Furthermore, radiation exposure involves people during the experiment. On the contrary, the simulation technique for examining radiation interactions is radio-logically safer, less timeconsuming, cost-effective, and applicable for all desired radiation sources. Through 48.86 mCi 662 keV Caesium-137 gamma-ray source; shielding experiment as well as simulation of it with MCNPX were performed for three shielding materials Lead, Copper, and Aluminum. These materials were placed in front of the gamma source and the emergent radiation was counted in a Geiger- Muller detector to understand the attenuation quality of these materials to each other. These courses of action were simulated utilizing the MCNPX code version 2.7.0 and the results likewise gave and looked at that of the experiment. There are huge similarities of shielding behavior between MCNPX simulation and experiments for the three absorbing materials. The modeled geometry of this MCNPX simulation could be used for future approaches of new designs and structures of radiation shielding, especially where no analogous experimental data exist

[Display omitted] • Sm 2 O 3 and graphene/Sm 2 O 3 nano-structures were prepared by the hydorthermal method. • Different physical properties and sheilding parameters were examined. • By experimental and simulation method, some sheilding parameters were calculated. • All protection parameters are in good agreement in both investigated methods. Nowadays, utilizing of alternative materials instead of lead in the environmentally sensitive and nontoxic material research in radiation shielding has attracted a lot of attention. Within this study, pure samarium oxide and samarium oxide/graphene nanostructures were successfully synthesized consecutively by facile hydrothermal method. The various physical properties of these materials were investigated using the conventional methods of energy dispersive X-ray spectroscopy (EDX), UV–Visible spectrophotometry, X-ray diffraction (XRD), Fourier transform infrared spectroscopy (FTIR), Raman spectroscopy, and field emission scanning electron microscopy (FESEM). XRD result verified cubic phase of Sm 2 O 3 ; however, the addition of graphene modified slightly the main structure. The result of FESEM showed the connection between the graphene nanoplates and samarium oxide nanoroads. The verification of the elemental presence for the both samples was performed through EDX analysis. The main factors of gamma protection properties such as mass attenuation coefficients (MAC), mean free path (MFP), half value layer (HVL), tenth value layer (TVL) and linear attenuation coefficients (LAC) have been measured for Sm 2 O 3 /graphene sample. They were 0.59 cm2/g, 0.23 cm, 0.16 cm, 0.54 cm, and 4.2 cm−1, respectively. According to these factors, it can be concluded that utilizing of graphene/Sm 2 O 3 as a gamma ray protector can be useful. In addition to the experimental examination, simulation with GEANT4 simulation code was also used for both samples to examine the shielding parameters. The experimental and simulation attenuation for Sm 2 O 3 /graphene was about 19.2 % and 18.6 %, respectively. [ABSTRACT FROM AUTHOR]

In order to solve the problem of poor thermal conductivity of polymer‐based radiation shielding composite materials, h‐BN@PDA@PbWO4 hybrid powders were prepared by combining h‐BN with high thermal conductivity and PbWO4 with γ shielding. With the assistance of polydopamine, PbWO4 particles were synthesized in situ on the h‐BN surface. The effects of h‐BN@PDA@PbWO4 on thermal conductivity, γ‐ray shielding, and mechanical properties of chloroprene rubber were studied. The results showed that the hybrid particles had better dispersibility than the pure mixing of h‐BN and PbWO4 in chloroprene rubber and significantly improved the thermal conductivity gamma‐ray shielding performance and mechanical properties of CR composites. When the filler content of the hybrid powder reaches 40 wt%, the thermal conductivity of the composite is about 3.16 times that of the pure CR. The γ shielding rates at 86.5 KeV and 105.3 KeV photon energies increase by 14.14% and 17.61% compared with the pure CR. Compared with pure CR, the tensile strength of the composites increased by 4.79 MPa, and the elongation at break decreased slightly. These were because h‐BN@PDA@PbWO4 shows had an excellent synergistic effect in CR substrate. The new kind of CR/h‐BN@PDA@PbWO4 composite can be used for thermal management and gamma shielding. [ABSTRACT FROM AUTHOR]

Glass samples with (86-x)TeO2 -- 12Nb2O5- x(Ta2O5) -1.0La2O3 where x = 1.0 (glass TNTL1), 5.0 (glass TNTL2), 8.0 (glass TNTL3), and 10 (glass TNTL4) mol% composition were synthesized by a melt quenching technique. The gamma- ray attenuation parameters of TNTL system such as MAC, LAC, HVL, MFP, Zeff, and Neff were analyzed in this study in order to better understand the effect of Ta2O5 on photon absorption.Within the 190-2500-nm wavelength range, the optical properties of prepared TNTL glasses were also evaluated. It was observed from the optical absorption spectra that all glass samples studied had good optical transparency. The findings indicated that adding Ta2O5 to glass enhances the gamma protection ability as well as the optical properties. The densities of the samples ranged from 5.66 to 6.49 g/cm3, depending on the Ta2O5 concentration. Sample TNTL4 had the best preformace, according to the results recorded. [ABSTRACT FROM AUTHOR]

This paper examines gamma-ray shielding properties of SBC-Bx glass system with the chemical composition of 40SiO2–10B2O3–xBaO–(45-x)CaO– yZnO– zMgO (where x = 0, 10, 20, 30, and 35 mol% and y = z = 6 mol%). Mass attenuation coefficient (μ/ρ) which is an essential parameter to study gamma-ray shielding properties was obtained in the photon energy range of 0.015–15 MeV using PHITS Monte Carlo code for the proposed glasses. The obtained results were compared with those calculated by WinXCOM program. Both the values of PHITS code and WinXCOM program were observed in very good agreement. The μ/ρ values were then used to derive mean free path (MFP), electron density (Neff), effective atomic number (Zeff), and half value layer (HVL) for all the glasses involved. Additionally, G-P method was employed to estimate exposure buildup factor (EBF) for each glass in the energy range of 0.015–15 MeV up to penetration depths of 40 mfp. The results reveal that gamma-ray shielding effectiveness of the SBC-Bx glasses evolves with increasing BaO content in the glass sample. Such that SBC-B35 glass has superior shielding capacity against gamma-rays among the studied glasses. Gamma-ray shielding properties of SBC-B35 glass were compared with different conventional shielding materials, commercial glasses, and newly developed HMO glasse. Therefore, the investigated glasses have potential uses in gamma shielding applications.

This work investigated the effects of a radiation-protective filler, namely bismuth oxide (Bi2O3), and blowing agents, namely azodicarbonamide (ADC) and oxy-bis (benzene sulfonyl) hydrazide (OBSH), on gamma attenuation and the mechanical, physical, and morphological properties of cellular natural rubber (NR) composites for potential use as light-weight and lead-free gamma-shielding materials. The contents of Bi2O3 were varied from 100 to 300 and 500 parts per hundred of rubber by weight (phr) and the contents of ADC or OBSH were varied from 0 to 8 and 16 phr. The results indicated that the addition of Bi2O3 enhanced the overall gamma-shielding ability, density, tensile modulus, and hardness (Shore OO), but lowered the tensile strength and elongation at break. On the other hand, the addition of ADC or OBSH resulted in decreases in the density, linear attenuation coefficient (μ), and overall tensile properties but an increase in the mass attenuation coefficient (μm), with ADC producing better mechanical properties than samples with OBSH. In addition, investigations on the properties of the cellular Bi2O3/NR composites under additional 35 kGy and 70 kGy gamma irradiation revealed that the irradiated samples had increased density, tensile modulus, and hardness (Shore OO), but decreased tensile strength, elongation at break, and μm after such ageing. In conclusion, the overall results suggested that the developed cellular Bi2O3/NR composites not only had efficient and promising gamma-shielding and mechanical properties but also offered comfort and light-weight to users, which could potentially reduce discomforts caused by wearing heavier conventional radiation-protective equipment. [ABSTRACT FROM AUTHOR]

Gamma radiation shielding of baked and unbaked granite bricks produced with 0%, 10%, 20%, 30%, 40%, and 50% of kaolin powder were experimentally and theoretically assessed for possible deployment in liquid radioactive waste storage. A 3 × 3 inches NaI(Ti) detector and WinXCOM program were used to measure the linear attenuation coefficients at different energies. Elements composition of samples were analyzed using particle induced X-ray emission (PIXE) spectroscopy. Results show that adding kaolin to granite positively reduced the liquid permeability coefficients of the bricks but negatively reduced the shielding properties of the bricks. Optimum results were obtained from unbaked sample of granite brick produced with 50% of micro scale kaolin powder (GK50) with mass attenuation coefficient of 0.0663, 0.0572 and 0.0552 cm² .g−1, radiation protection efficiency (RPE) of 38.36%, 34.11% and 33.13% for radiation energies levels of 661.6, 1173.2, and 1332.5 keV respectively and liquid permeability coefficient of 6.53 × 10−11 m.s−1 . The study concludes that all brick samples were thermally stable, good in gamma radiation shielding and efficient in liquid radioactive waste immobilization. [ABSTRACT FROM AUTHOR]

This work aimed to investigate the impact of Lead-fluoride based glasses via theoretical and simulation techniques on mechanical and radiation shielding parameters. Accordingly, Bi2O3 was blended with TeO2–B2O3–PbF2 glasses by using melt-quenching method. Using Fluka Monte Carlo code, the radiation shielding properties have measured. Moreover, Comparatively higher density PbF80 = 6.163 g/cm3 with 80 mol % Bi2O3, greater µ, µm and Zeff and lower T1/2, λ, tenth value layer values achieved for TeO2–B2O3– PbF2/Bi2O3 glass pointed it out as the best shield of gamma. Besides, the computed effective removal cross-sections against fast neutrons (ΣR) observed that the PbF80 sample has commensurately greater with a value 5.2954 (cm−1). The results observed that the variation PbF2/Bi2O3 improves the gamma protection ability of Lead-fluoride based glasses. The incremental of Bi2O3 at the expense of PbF2 increases the density and the packing density of the glasses and hence increase the longitudinal modulus-L, shear modulus-S, bulk modulus-K, and Young's modulus-Y from 15.89 to 25.9 GPa, from 8.49 to 12.09 -GPa, from 4.58 to 9.77 GPa, and from 15.74 to 25.69 GPa, respectively. The increase of the elastic moduli can be attrinuted to the glass former role of Bi2O3. The results indicate that the highest PbF2/Bi2O3 ratio encoded PbF00 has the best shielding and mechanical competence with measurable physical properties. [ABSTRACT FROM AUTHOR]

Gamma-ray, fast neutron and charged particle shielding characteristics of Dy3＋ activated glasses with composition 15Li 2 O-25BaO-(40-x)B 2 O 3 -20P 2 O 5 -xDy 2 O 3 (x = 0, 0.2, 0.4, 0.6, 0.8, and 1.0 mol %) are analyzed in a wide incident energy for the first time. For gamma-ray shielding analysis, mass attenuation coefficient (MAC), mass energy absorption coefficient (μ e n), linear attenuation coefficient (LAC), mean free path (MFP), half-value layer (HVL), atomic cross-section (ACS), electronic cross-section (ECS), effective atomic number (Z e f f), equivalent atomic number (Z e q), effective conductivity (C e f f), effective electron density (N e f f), buildup factors (EABF and EBF), and kinetic energy released per unit mass of the absorbing material (KERMA) are calculated by using Phy-X/PSD and PAGEX softwares. For fast neutrons, fast neutron removal cross-section (FNRCS) is computed for all glass samples. For charged particle shielding analysis, mass stopping power (MSP), projected range (Rp), radiation yield (Ry), Z e f f and N e f f are computed using SRIM, ESTAR and PAGEX softwares. It is found that the glasses with increasing Dy3＋ have higher shielding potential. This suggests that the LBPDy1.0 sample has a potential use as shielding material for various applied fields. • Photon and neutron protection parameters of Dy3＋ activated glasses have been calculated. • Charged particle protection parameters of Dy3＋ activated glasses have been calculated. • Dy3＋ activated glasses with a composition of 15Li 2 O-25BaO-(40-x)B 2 O 3 -20P 2 O 5 -xDy 2 O 3 can be used as shielding materials. [ABSTRACT FROM AUTHOR]

Glasses are important materials due to its utilization in many different fields. As the radiation started to be used in many field its protection becomes vital for human health. Thus in this study, the gamma and neutron shielding characters of glasses formulated as 90 %(Se)- (10-x)% (Te)-x%(Ag) where x = 5,6,7 (mol%) glass were investigated. This is done to evaluate the ability of glasses to act as shielding materials. The mass attenuation coefficient (MAC) was computed by the Phy-X/PSD program for energies ranging from 0.015 to 15 MeV and from the computed MAC values the other significant shielding parameters such as effective atomic number (Z eff) and effective electron density (N eff) were obtained for all glass samples. The fast neutron removal cross-sections of all glass samples were also obtained. • The gamma and neutron shielding characters of glasses were investigated. • The mass attenuation coefficient (MAC) was computed at energies of 0.015–15 MeV. • Effective atomic number (Zeff) and effective electron density (Neff) were obtained. • The fast neutron removal cross-sections of all glass samples were also obtained. [ABSTRACT FROM AUTHOR]

This study aimed to have a wide-range investigation on changes of optical, structural, mechanical durability and nuclear radiation attenuation properties of barium borosilicate glasses through BaO reinforcement. Accordingly, gamma-ray attenuation parameters of a series of glasses with the nominal composition of xBaO-(50-x)B 2 O 3 –20NaO–15SiO 2 –10CaO–5Al 2 O 3 (x= 0, 5, 10, 20 and 30 wt%) were extensively evaluated using experimental, simulation and theoretical methods. The linear attenuation coefficient (LAC) of glasses were experimentally measured using NaI (Tl) (3×3 inch) detector. LAC values of Ba00, Ba05, Ba10, Ba20 and Ba30 glasses were reported as 0.4951, 1.0129, 1.5780, 2.8795 and 4.4203 at 81 keV and 0.1030, 0.1084, 0.1148, 0.1278, and 0.1397 at 2614 keV, respectively. Accordingly, obtained results were compared with the XCOM program and FLUKA general purpose Monte Carlo simulation code at photon energies from 81 to 2614 keV. Furthermore, LAC values were used to calculate other related parameters including MAC, X 1/2 , and λ. Comparatively higher density (3.652 g/cm3), greater LAC, MAC and lower both X 1/2 , and λ values achieved for Ba30 glass indicated it as a better gamma shield. The outcomes of mechanical durability investigations showed that replacing B 2 O 3 with BaO resulted in a decrease in the flow movement that leads to an increase in the density of the crosslinking as well as the observed difference in the atomic mass B and the atomic mass of Ba and thus increase the hardness Moreover, the vibrational modes of theses samples are active in four IR spectral peaks related to the compositions. Moreover, the optical parameters of these samples have been calculated. The results also showed that an enhancement of the transmittance was observed since optical band gap increases as BaO content increases. [ABSTRACT FROM AUTHOR]

Isophthalic polyester resin was reinforced by using different metal oxides (lead(II)oxide, tungsten(VI)oxide and ferric oxide) and different reinforcement ratios (10–50%). Ionizing electromagnetic radiation shielding performance of the composites were determined by gamma spectrometric techniques for three different ionizing electromagnetic radiation (IEMR) energy regions (60–392, 662–898, 1173–1836 keV). Density evaluation, FTIR analysis, SEM studies were carried out. The IEMR attenuation performances of the composites were determined with gamma spectroscopy and found to be satisfying. These composites give better performance with respect to reference lead, especially in the case of the applications that weight of IEMR shield is important. [ABSTRACT FROM AUTHOR]

To assess the relationship between gamma ray shielding performance and glass-melting conditions, an extensive investigation was performed on different types of fluoro-sulfo-phosphate (FPS) glasses. Four different FPS glasses melted in Al and Pt crucibles were modeled in MCNPX (version 2.6.0) general purpose Monte Carlo code. For this aim, a gamma-ray transmission setup has been modeled with essential simulation equipment. The mass attenuation coefficients for each glass sample in different melting-condition were determined. The obtained mass attenuation coefficients were utilized for determination of Half Value Layers (HVL) and mean free paths (mfp). Next, energy absorption buildup factors (EABF) and exposure buildup factors (EBF) of investigated FPS glasses were determined by using geometric-progression (G-P) fitting method. To evaluate the effect of glass-melting conditions on fast neutrons, effective removal cross sections of FPS glasses were calculated. Finally, an extensive comparison between the superior samples of FPS glasses melted in Al and Pt crucibles were performed. The results showed that GPT-4 sample melted in Pt crucible has relatively higher radiation shielding properties than GAL-2 sample which melted in Al crucible. In addition to material additive, the results showed that even glass-melting conditions has a significant impact on radiation shielding properties of glass material. It can be concluded that, in addition to the most effective material additives into glass structures to improve radiation shielding performances, providing them in the most favorable melting-conditions can provide a versatile improvement. [ABSTRACT FROM AUTHOR]

This paper has focused on the investigation of gamma and neutron attenuation properties of Li 2 O–B 2 O 3 –P 2 O 5 –TeO 2 glass system. Gamma shielding parameters such as mass attenuation coefficients ( μ m ), effective atomic numbers (Z eff), half value layers (HVL), tenth value layers (TVL), mean free path (MFP), effective electron density (Ne), equivalent atomic numbers (Z eq) of investigated glass samples have been calculated in a wide photon energy range of 0.02–20 MeV using MCNPX general purpose Monte Carlo code. The calculated results for mass attenuation coefficients were compared with XCOM. In addition, exposure buildup factors (EBF) and energy absorption buildup factors (EABF) of investigated glasses were determined by using the G-P fitting method. The results showed that sample 9 with the highest density had the lowest HVL, TVL and MFP values among the investigated glasses. Moreover, effective removal cross-sections (Σ R) and transmission factors (TFs) have been calculated. The obtained results have shown that the TeO 2 additive into glass samples had a positive effect on the nuclear protection performance of the investigated glass samples. It can be concluded that the impact of TeO 2 additive for nuclear radiation shielding applications can be further investigated in different types of glass systems. [ABSTRACT FROM AUTHOR]