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The use of geopolymer in place of ordinary Portland cement for concrete design and constructure is gaining attraction due to environmental and health considerations. Geopolymers must have high gamma radiation shielding competence in order for them to be useful for radiation shielding concrete. In an attempt to improve the gamma absorption capacity of a metakaolin-based geopolymer matrix, 10 % (GEO-10Y), and 20 % (G-20Y) yttria (Y2O3) was mixed with GEO through a solid-state reaction process. In this study, the influence of adding yttria on the physical and gamma shielding parameters of GEO was investigated. The densities of GEO, GEO-10Y and GEO-20Y were obtained as 2.28, 2.52 and 2.37 g/cm3, respectively. Through simulation using FLUKA code, the mass attenuation coefficients (MAC) and other relevant shielding quantities were estimated. The MACs of GEO, GEO-10Y, and GEO-20Y were within the range of 0.0213–6.6429 cm2/g, 0.0282–13.3923 cm2/g, and 0.0291–14.5136 cm2/g, respectively. The addition of yttria improved the gamma photon shielding competence of the metakaolin-based geopolymer by increasing the MAC and reducing photon buildup factors within 15 keV–15 MeV photon energy range. The shielding effectiveness of the yttria-doped GEO compares well with conventional shielding materials. Yttria-doped geopolymer can be used to produce effective and environmentally-friendly gamma shielding concrete.

Water from the industries contains various organic effluents which are needed to be removed. Photocatalysis is an efficient method to degrade organic effluents that contaminate water and harmfully affect the environment. This study presents the structural, optical characteristics, and photocatalytic activity of the CuO/MoS2 and their composite with gCN. The hydrothermal approach was employed to fabricate MoS2 nanoflowers, and the co-precipitation method to fabricate CuO. The composite with gCN was prepared successfully using an ultrasonication approach. The physio-chemical properties of fabricated photocatalysts were investigated by various characterization techniques. SEM analysis revealed the nanoflower morphology of the prepared MoS2 sample. The photocatalytic activity was examined by the photodegradation of methyl orange dye and phenol. CuO/MoS2@gCN photocatalyst showed 85.14 % degradation of methyl orange and 63.50 % degradation of phenol. Also, the rate constant of CuO/MoS2@gCN was found to be 0.051 min−1 for MO dye and 0.02 min−1 for phenol, which is higher than other synthesized samples. The scavenging experiment was carried out to identify the most photoactive species involved in the organic pollutants photocatalytic degradation. Electrons served as the primary photoactive species in photocatalysis. Consequently, it is concluded from the results that CuO/MoS2@gCN could be employed as an efficient photocatalyst for wastewater treatment.

Based on the simplistic two-step preparation method, a Cu2O/TiO2 junction was synthesized by electrodepositing a Cuprous Oxide layer on Titanium Oxide thin films at different deposition potentials. The thin films and junction were characterized for their structural, morphological, optical, and electrical properties using X-ray diffraction, Scanning Electron Microscopy, UV–visible spectroscopy, and Electrochemical Impedance Spectroscopy. The XRD analysis of the Cu2O/TiO2 junction indicated no sharp diffraction peaks of TiO2, only Cu2O peaks were observed. The Scanning Electron Microscopy also demonstrated that the Cuprous Oxide thin films possessed three-sided pyramidal structures on their surface. The band gaps of Cu2O and TiO2 thin films were calculated as 2.2 eV and 3.3 eV respectively by using Tauc’s plots. Electrochemical impedance spectroscopy revealed reduced interfacial charge transfer resistance and a boost in charge carrier generation in fabricated junctions (grown at −0.6 V). The flat band potentials and carrier concentrations of the fabricated thin films and their junction were calculated using Mott-Schottky analysis. Meanwhile, charge transfer resistance, solution resistance, constant phase element, and other circuit parameters of the electrochemical cell were studied using Nyquist plots.

In this manuscript, we have investigated the dielectric and antibacterial potential of hydrothermally synthesized ZnMnO nanoparticles. The synthesized nanoparticles were annealed at various temperatures ranging from 450 to 650 °C with a step of 50 °C to modulate the structural, vibrational, dielectric, and antibacterial properties. XRD data confirmed the hexagonal structure of the synthesized samples and crystalline size was decreased to 4.8 nm at annealing temperature 600 °C. The lattice structure was further verified by Raman spectroscopy measurements, which strongly verified the XRD data due the presence of ZnMnO vibrational modes. The dielectric measurements revealed that the dielectric constant and los tangent were found to be increased with the increase annealing temperature and decreased with frequency, while a.c conductivity has an increasing trend with both parameters (temperature and frequency). The plot of real and complex parts of impedance against frequency demonstrated that both parameters decrease with the increased in frequency. But when we analyzed the behavior of the real part of impedance against the annealing temperature, a degradation in real part behavior is observed. The antibacterial activity of ZnMnO nanoparticles was determined by using the disc diffusion method against E. coli bacteria, which was grown on a Petri dish at room temperature for 24 h. This observation revealed that the samples annealed at 450 °C and 550 °C show remarkable antibacterial sensitivity as compared to other samples. It is concluded that crystalline size of 20 nm is found to be optimal value for good anti-baterial behavior.

The study aimed to establish a correlation between the photocatalytic degradation of Congo red (CR), Crystal violet (CV) dyes and Diclofenac sodium (DS) drug by copper, terbium substituted nickel ferrite (CuxNi1-xTbyFe2-yO4) and MXene (CTNF/MXene) composite where (x, y = 0.1). Terbium and copper doping reduced crystallite size, band gap energy, improve visible light absorption and impede electron-hole pair recombination. Superior complexation ability of terbium forces more pollutants to adsorb on the surface of photocatalyst and hence more degradation. Results indicated that MXene, acting as a co-catalyst, effectively lowered the charge recombination rates by electron trapping and enhanced the visible light absorption, improving the photocatalytic activity. CTNF/MXene composite exhibited greater rate constant and photocatalytic degradation of CR (91 %), CV (77 %) and DS (81 %) as compared to NF, CNF, TNF, CTNF. The increased surface area of CuxNi1-xTbyFe2-yO4 with MXene and reduced electron-hole pair recombination are possible factors for its successful use as photocatalyst.

Designing highly efficient and durable multicomponent heterostructured composites as catalytic materials for concomitant hydrogen evolution reaction (HER) and oxygen evolution reaction (OER) is highly desirable. Researchers all over the world are continuously working to develop such materials. Herein, CNTs wrapped CoFe2O4/CoFe LDH (CoF/CoFe LDH@CNTs) ternary composite is synthesized by hydrothermal and ultra-sonication routes. Numerous methods, including X-ray diffraction (XRD), scanning electron microscopy (SEM), cyclic voltammetry (CV), electrical Mott-Schottky, and electrochemical impedance spectroscopy (EIS) are employed to study structure, morphology, flat band potential, and electrochemical properties of prepared samples. In terms of water splitting performance, CoF/CoFe LDH@CNTs composite showed predominant performance for both HER and OER activities, as compared to its analogs (CoF and CoF/CoFe LDH). Faster electron transfer is also exhibited by CoF/CoFe LDH@CNTs, as it possesses a lower Tafel slope. For OER, CoF/CoFe, LDH@CNTs require a small overpotential of 170 mV to reach a current density of 10 mA cm−2 in 1 M KOH, with a Tafel slope of 42 mV dec-1. Similarly, for HER an overpotential of 218 mV is required to drive 10 mA cm−2 with a small Tafel slope of 31 mV dec-1. Impedance studies show a small value of charge transfer resistance (Rct = 1.11 Ω) for CoF/CoFe, LDH@CNTs. Significant electrochemical performance for CoF/CoFe, LDH@CNTs for both half-reactions (OER and HER) is ascribed to the synergy among electrochemically active CoF and CoFe LDH, and a highly conductive network of CNTs. The present strategy improves the electrochemical performance of electrochemical systems relevant to energy applications.

In this study, the gamma-photon, neutron, and charged particle interaction quantities for SiO2–P2O5–CaO–Na2O–CaF2 bioactive glasses were evaluated with the objective of estimating the effect of CaF2 on the physical and radiation responses of the bioactive glasses involved. The physical features (e.g. glass density) were increased as the CaF2 increases in the samples. The gamma mass-attenuation coefficient (μ/ρ) of the glasses was estimated for photon energies 0.015–15 MeV using the XCOM database and the FLUKA Monte Carlo simulation procedure. The total stopping powers (TSP) and range of charged particles (electrons, protons, α-particles, and C6+ ions) were estimated with the aid of ESTAR (for electrons only) and the SRIM Monte Carlo code (for protons, α-particles, and C6 + ions). In addition, the fast (ΣR) and thermal (TN) neutron cross-sections were computed for the glasses using standard theoretical models. The μ/ρ values of the SPCNCF glasses were within 0.0216–8.7469, 0.0217–9.2151, 0.0219–10.0588 and 0.0222–11.1264 cm2/g for SPCNCF1, SPCNCF2, SPCNCF3 and SPCNCF4, respectively. The half-value layers had minimum values of 0.02936, 0.02767, 0.02499, and 0.02215 cm for SPCNCF1, SPCNCF2, SPCNCF3, and SPCNCF4, respectively, at 0.015 MeV. Analysis of the estimated photon interaction parameters showed that the gamma radiation attenuation prowess of the glasses improved with CaF2 content. The same trend was observed for charged particles. The TSP of electrons is maximum at 0.015 MeV with values of 12.82 for SPCNCF1 and SPCNCF2, 12.76 for SPCNCF3 and 12.71 MeV cm2/g for SPCNCF4. The values of ΣR were equal to 0.0896, 0.0896, 0.0897 and 0.0900 for SPCNCF1, SPCNCF2, SPCNCF3, and SPCNCF4, respectively. The increase in the weight proportion of CaF2 also improved the fast neutron removal and total thermal neutron interaction capacities of the SPCNCF glasses. The SPCNCF glasses showed better shielding competence compared to some conventional shields such as RS 253 and RS 253 G18 commercial shielding glasses, concrete samples, and polymers.

This research is carried out to establish a link between thermoelectric properties of Copper Nitride (Cu3N) thin films with its growth parameters. A series of Cu3N thin films is synthesized by thermal evaporation technique on glass substrate using different source to substrate distances (21–27 cm) by vacuum tube furnace. X-ray diffraction (XRD), Raman spectroscopy, and Scanning Electron Microscopy (SEM) were used to evaluate different structural, vibrational and morphological properties. A 25 cm source to substrate distance is found to be an optimal value for the highest Seebeck coefficient and electrical conductivity. It is further observed that the Cu3N phase was fully developed at this optimal source to substrate distance. These findings are justifiable because at optimal distance, nitrogen atoms are able to acquire required thermal energy which needed for bonding with Cu atoms.

Tungsten oxide (WO3), Iron and vanadium co-doped tungsten oxide (FeVWO3), and the composite of iron and vanadium co-doped tungsten oxide with graphitic carbon nitride (FeVWO3@g-C3N4) were prepared for the photocatalytic study. WO3 and FeVWO3 were synthesized by co-precipitation, and the composite FeVWO3@g-C3N4 was synthesized by an ultra-sonication approach. All the prepared materials were analyzed by different techniques. Structural study was done by XRD, functional group analysis by FTIR, and SEM was used for the morphological study of the nanoparticles. EIS measurements were done to investigate the electrical properties of fabricated materials. Photocatalysis was performed for the band gap analysis. Pendimethalin (PM) a herbicide and aspirin (pharmaceutical product) were used in photocatalysis and degraded by the prepared photocatalysts (WO3, FeVWO3, and FeVWO3@g-C3N4). WO3 and FeVWO3 have 2.62 eV and 2.34 eV Eg values of band gap, respectively. FeVWO3 has a lower Eg value than WO3. The decrease is due to the doping, and generation of further energy levels in the band gap of the pure sample, and these energy levels cause changes in the electronic structure of the sample. The composite shows a high degradation efficiency. The percentage degradation of pendimethalin and aspirin by FeVWO3@g-C3N4 was 82.26 % and 92.84 %. It is because of the presence of g-C3N4 which provides greater surface area for better degradation efficiency.

Radiation shielding incorporates material between the radioactive source and environment to decrease exposure to hazardous radiation. It remains to be seen whether the addition of nanoparticles effectively increases the protection of tellurite glass system from further degradation under irradiation conditions. This study revealed the gamma radiation effects on tellurite glass. The tellurite glass samples were irradiated with 50 kGy and 100 kGy gamma ray, and subsequently analysed using X-ray diffractometer (XRD), atomic force microscopy (AFM), and ultraviolet–visible spectroscopy (UV–Vis). Gamma radiation increased the creation of non-bridging oxygen (NBO) and caused colour change on TZNETi and TZNETiAl glasses. Consequently, the addition of aluminium oxides (Al2O3) was found to lower the density of glass systems. The glass samples surface roughness increased, while the optical transmission spectra decreased after 50 kGy of gamma ray irradiation. Nevertheless, the glass system maintained its transparency even after irradiation. The mass attenuation coefficient (MAC) values represented the shielding effectiveness demonstrated by the investigated glass with the addition of Al2O3. The physical, structural, optical, and radiation shielding properties showed that 69.1TeO2–20ZnO–9Na2O–1Er2O3–0.3TiO2–0.6Al2O3 (TZNETiAl) sample exhibited strong shielding properties amongst the fabricated tellurite samples.

In this study, the gamma-ray photon, electron, proton, helium ion, carbon ion, thermal neutron, and fast neutron interaction parameters of the (70-x)(Bi2O3 + ZnO) + x(V2O5 + TeO2) + 20B2O3 + 6.5SiO2 + 2.5Al2O3 + 1(CeO2 + Sb2O3) glass system were estimated with the aim of assessing their radiation shielding potentials. The mass attenuation coefficients (MACs) of the glasses were estimated for photon energies between 0.015 and 15 MeV using the PHITS simulation code and XCOM software. The stopping powers of charged radiation such as electrons, protons, α-particles, and carbon ions were also estimated by Monte Carlo simulation of particle transport using PHITS. The narrow beam transmission simulated using PHITS yielded values of MAC that were not so different from those from XCOM. The MACs of B/V-ZBVSA1 vary from 0.039–90.747 cm2/g, while those of B/V-ZBVSA2, B/V-ZBVSA3, and B/V-ZBVSA4 vary from 0.035–69.724, 0.036–73.088, and 0.037–70.597 cm2/g, respectively. The HVL of the glasses varied from 0.011–2.56 cm, 0.019–3.69 cm, 0.017–3.31 cm, and 0.017–3.36 cm for B/V-ZBVSA1 – B/V-ZBVSA4, respectively The effective atomic number varied within the limits: 28.36–76.06, 19.67–67.91, 22.14–68.70, and 22.39–68.08 for BV-ZBVSA1 – BV-ZBVSA4, respectively. The stopping powers (Sp) of electrons in BV-ZBVSA1, BV-ZBVSA2, BV-ZBVSA3, and BV-ZBVSA4 were in the range 1.219–8.043 MeVcm2/g, 1.295–9.306 MeVcm2/g, 1.264–8.859 MeVcm2/g, and 1.257–8.793 MeVcm2/g correspondingly. Comparatively, the Sp of protons, α-radiation, and carbon ions follows the order: BV-ZBVSA2 > BV-ZBVSA3 > BV-ZBVSA4 > BV-ZBVSA1. Also, the value of ΣR for BV-ZBVSA1, BV-ZBVSA2, BV-ZBVSA3, and BV-ZBVSA4 was 0.1171, 0.1126, 0.1133, and 0.1103 cm−1 accordingly, while the corresponding total cross-section of thermal neutrons was 67.6227, 46.8356, 59.1179, and 56.6994 cm−1. The present glasses showed superiority in absorbing photons and neutrons compared to some existing shields and previously recommended glasses. The present glassy samples, thus, can be adopted for radiation protection purposes, among others in radiation facilities.

This work explains the first-principle computational inquiry of physical features of BWF3 (W = S and Si) halide-Perovskites compounds. With the aid of the WIEN2K code, our recent computation solely relies on Density Functional Theory (DFT). Using the equation of states made by Birch Murnaghan for optimization. The elastic factors are figure out and used to compute elastic characteristics, we found that both composites are structurally as well elastically stable. These substances exhibit strong resistance to plastic strain and are show ductility, scratch-resistant and anisotropic. BSF3 and BSiF3 are both metal-like substances, according to calculations made using the Tb-mBJ) potential approach. Density of states calculations are recycled to conclude how different energy states are involved in band structures. These compounds' band gap energies make it simple to study various optical characteristics. These chemicals exhibit strong absorption at high energy ranges. The compound BSF3 is transparent to incoming photons at low energies, while the complex BSiF3 is opaque. We have come to the conclusion that the compounds BSF3 and BSiF3 can be employed for high-frequency UV device applications as a result of our study into their optical properties. For the first time, our computational effort is calculated to investigate these substances that have not yet been experimentally proven to our satisfaction.

WO3 effects on neutron and ionizing radiation defending factors of ternary tellurite-based glass blocks with molecular formula 80TeO2 –(20-x)WO3 – xK2O; x = 0–20 mol% (denoted as TKW-glass) has been reported via Phy-X theoretical calculations and Geant4 simulation code. Correlations between shielding factors and kinetics properties of the investigated glasses at different photon energy have been examined. The highest values of mass (MAC) attenuation coefficient were noted at 15 keV of the examined TKW-glass materials with the values of 38.408, 44.388, 49.855, 54.872, 59.492 cm2/g for TKW-0, TKW-5, TKW-10, TKW-15, and TKW-20, respectively. Generally, these values of the TKW-glasses obey the sequence: (TKW-0)MAC< (TKW-5)MAC < (TKW-10)MAC < (TKW-15)MAC < (TKW-20)MAC. The highest mean free path (MFP) values of TKW-glasses were registered at 15 MeV with the values of 6.101, 5.591, 5.097, 4.647, and 4.302 cm for TKW-0, TKW-5, TKW-10, TKW-15, and TKW-20, respectively. The two parameters half value layer (HVL) and MFP follow the pattern: (TKW-0)HVL, MFP > (TKW-5)HVL,MFP > (TKW-10)HVL,MFP > (TKW-15)HVL,MFP > (TKW-20)HVL,MFP. The maximum values of effective atomic number (EAN) took place at gamma energy of 15 keV corresponding to 44.35, 48.86, 52.63, 55.83, and 58.58 for TKW-0, TKW-5, TKW-10, TKW-15, and TKW-20, respectively. The trend of the buildup factors was similar for all of the glass specimens. The fast neutron removal cross-section (ΣR) enhanced as WO3 content increased in the specimens. Thus, the peaked value of ΣR is 0.1059 cm−1 was noted in the TKW-20 sample. Mechanical properties, neutron and γ-rays protection parameters were observed to improve with enhanced WO3 mol% in the TKW-glasses. The current results bear their utilization for neutron and gamma protection purposes.

Current work presents the synthesis of B2O3–Gd2O3–Li2O–Na2O–LiF‒Sm2O3 glass system via melt-quench approach and scrutiny of its mechanical, thermal, structural, physical, and nuclear radiation attenuation aspects. Raman scattering and Fourier transform infrared spectra revealed B–O stretching modes of BO4 groups linked to BO3 units with nonbridging oxygen atoms and BO3 and BO4 units' existence in the glass structure. By differential scanning calorimetry, glass transition and crystallization temperatures are identified. Relevant analysis showed all glasses' good thermal stability where glass transition temperature varied at 372–407 °C range. ΣR (fast neutron removal cross-section) and for energy 0.025 eV neutrons σT (total cross-section) are computed. In all glasses, 49.25 B2O3–10Gd2O3–10Li2O–10Na2O–20LiF-0.75Sm2O3 (mol%) sample holds higher ΣR (= 0.10207 cm−1). 48B2O3–10Gd2O3–10Li2O–10Na2O–20LiF–2Sm2O3 (mol%) glass possesses greater σT (= 736.675 cm−1) for thermal neutrons, hinting at added Sm2O3's favorable influence as Sm owns a better ability for neutron absorption than B. By Phy-X/PSD, μ/ρ (mass attenuation coefficient) is obtained at photon energy extent 15 keV‒15 MeV. Sm2O3 inclusion from 0 to 2 mol% minorly enhanced the μ/ρ values. Buildup factors estimated via geometric progression fitting method at 1–40 mean free path and energy 0.015–15 MeV span are maximal at medium energy region owing to Compton scattering process. 48B2O3–10Gd2O3–10Li2O–10Na2O–20LiF–2Sm2O3 (mol%) sample shows superior γ-ray blocking capacity in all glasses, suggesting Sm2O3's positive effect. Elastic moduli and Poisson's ratio are computed theoretically by bond compression and Makishima–Mackenzie models. It is identified that all glasses could tolerate longitudinal stress over shear stress.

This study comprises the combined effect of piezocatalytic and photocatalytic activity to obtain improved piezo-photocatalytic dye degradation efficiency in visible light. Single-phase Bi2VO5.5 powder was prepared through solid-state synthesis at 750 °C in 8 h. Time-dependent photocurrent responses were conducted to understand the phenomenon of charge carrier transport in visible light. Bi2VO5.5 powder sample demonstrated high photocatalytic efficiency and good reusability possessing a bandgap value of 2.13 eV. Bi2VO5.5 powder sample attained ∼70% and ∼58% degradation efficiency during photocatalysis and piezocatalysis respectively. The piezo-photocatalytic methylene blue dye attained ∼82% degradation efficiency in 240 min duration of visible light illumination. The scavenger test depicted holes (h+) as the principal active species in the piezo-photocatalytic dye degradation. There incurred no severe loss in photocatalytic efficiency even after 4 cycles which proclaims the reusability of the Bi2VO5.5 powder sample. A study on the kinetic rate constant with varying dye concentrations was conducted. With varied dye concentration of 5, 10, 15 mg/L, the kinetic rate constant obtained was 0.00528, 0.0030, and 0.00125 min−1, respectively. Germination index was found through a phytotoxicity test using vigna radiata seeds. Here visible light along with mechanical energy has been used to achieve higher MB dye degradation efficiency through piezo-photocatalysis.

The mechanical and shielding characteristics of (100 − x)% NaPO3−x% MoO3 (where x = 20,40,60) and (100-x)% NaPO3-x% WO3 (where x = 20,40,60) glass systems were studied to evaluate their ability to act as shielding materials. Using the Makishima-Mackenzie theory, the mechanical parameters of all glass samples and their dependence on the MoO3 content (mol%) for the first series and on the WO3 content (mol%) forthe second glass series were also investigated. The results showed thatthe mechanical properties and micro hardness were significantly enhanced by increasing the concentration of MoO3 from 20 to 60% for the first glass series and the concentration of WO3 from 20 to 60% for the second glass series. The shielding parameters of both glass series were also studied. The mass attenuation coefficient (μm) was computed by the Phy-X/PSD program for energies ranging from 0.015 to 15 MeV. The results are in excellent agreementwith the results calculated by the WinXCom software program and the results simulated by Geant4 Monte Carlo simulation. The computed μm values were used to deduce the other significant shielding parameters for all glass samples. The fast neutron removal cross-sections of all glass samples were examined and compared with those of standard materials. A strong correlation between the shielding parameters and the molar volume, oxygen packing density, and oxygen molar volume was found. The results revealed that thestudied glasses possessed superior shielding properties, especially the glass sample 0.4NaPO3-0.6MoO3 (mol%) which showed the most promising characteristics for radiation-shielding applications among the tested glasses.

The glass system 75B2O3 - 4.5ZnF2 – 0.5 Er2O3–(20−x) ZnO- x CeO2, x = (0 ≤ x ≤ 1 mol. %) was manufactured using a melt quenching process, with CeO2 substituted for ZnO in the glass matrix in concentrations ranging from 0 to 1 mol %. The Makishima–Mackenzie model and sound wave velocity measurements were used to evaluate the mechanical parameters and elastic characteristics of the examined glass system, respectively. The results showed that increasing CeO2 doping ratio from 0 to 1 mol% increased density, sound velocities, elastic properties, and microhardness from 5.80 to 9.01 GPa. Phy-X/PSD software was employed to assess the effect of replacing ZnO with CeO2 on shielding capacity. The obtained results revealed that replacing ZnO with CeO2 enhances shielding characteristics and the manufactured glass may be useful in shielding applications.

Three high entropy materials (La2O3+TiO2+Nb2O5+WO3+X2O3 coded as LTNWM1, LTNWM2, and LTNWM3 for X = B, Ga, and In) produced by aerodynamic containerless processing were evaluated for optical attributes, and their gamma-radiation absorption abilities were investigated in this report. Optical related parameters such as the molar refractivity (Rm), optical transmission (T), molar polarizability (αm), metallization criterion (M), reflection loss (RL), static (εstatic), and optical (εoptical) dielectric constants were estimated through standard expressions, while photon attenuation parameters were estimated from data from photon transmission simulations in FLUKA code and XCOM software. The attenuation parameters were calculated for a wide energy photon spectrum (15 keV–15 MeV). LTNWM1, LTNWM2, and LTNWM3 had Rm values of 18.94 cm3/mol, 21.45 cm3/mol, and 26.09 cm3/mol respectively. The αm has a value of 7.52 × 10−24 cm3 for LTNWM1, 8.51 × 10−24 cm3 for LTNWM2, and 10.35 × 10−24 cm3 for LTNWM3. The photon shielding parameters evaluated by FLUKA and XCOM are compatible. The mass attenuation coefficient for the glasses was between 0.0338 and 52.8261 cm2/g, 0.0336–58.0237 cm2/g, and 0.0344–52.1560 cm2/g for LTNWM1, LTNWM2 and LTNWM3, respectively. The effective atomic number at 1.5 MeV was 18.718, 20.857, and 22.440 for LTNWM1, LTNWM2, and LTNWM3, respectively. The shielding parameters of the HMOs compared to traditional gamma radiation absorbers are exceptional and highlight the potential of using them as optically transparent gamma-shields.

Ionizing radiation/charged particles shielding capacity of high density bismuth tellurite based glasses: (100-x)TeO2+xBi2O3 with x = 5(TB5), 8(TB8), 10(TB10), 12(TB12), and 15 (TB15) mol% have been examined. New Phy-X/PSD software has been applied to achieve this aim. The gamma radiation shielding parameters such as mass/linear attenuation coefficients (MAC/LAC), half value thickness (HVT), effective atomic number/electron density (Zeff/Neff) and mean free path (MFP) were estimated for thirteen (13) energies in the range of 0.2835–2.506 MeV associated with 60Co, 137Cs, 131I, and 22Na sources. Comparatively, the obtained values revealed that (MAC/LAC)TB5

In this study, a promising relationship between antibacterial zone and radiation attenuation properties was investigated in Ag2O doped bioactive glasses with a chemical composition of xAg2O–20Li2O–25TeO2-(55-x)B2O3 (where x = 0, 0.5, 1.0, 1.5, and 2.0 mol%). For this aim, a wide-ranging radiation attenuation characterization procedure was performed on Ag2O substituted bioactive glasses. The general-purpose Monte Carlo code MCNPX (v.2.7.0) was used to model bioactive glasses. The mass attenuation coefficients were calculated using a gamma-ray transmission setup. The coefficients obtained were used to determine other important attenuation properties. Finally, for particular behaviors, exposure (EBF) and energy absorption (EABF) build-up factors were calculated for specific attitudes of Ag2O substitutions in bioactive glasses during the interaction process. The results showed that there is direct relationship between Ag2O substitution amount and radiation attenuation properties. In addition to its well-behaviors on inhibition zone against bacterial occurrences, it can be concluded that increasing Ag2O would increase the gamma-ray attenuation properties of studied bioactive glass system.

Adequate shielding from ionizing radiations is essential in nuclear facilities because of such radiations’ adverse effects on humans in the event of unwanted or accidental exposure. In the current work, for four distinct compositions of B2O3-Li2O, Li2O-Na2O-K2O-B2O3, Gd2O3-SiO2-B2O3, and Bi2O3-Li2O-ZnO-B2O3 glass systems, neutron and γ-ray attenuation competencies combined with elastic features have been examined for feasible nuclear radiation protection purposes. ΣR (fast neutron removal cross-section) and for thermal energy neutrons σT (total cross-section) and SP (shielding percentage) were estimated. Comparably, in all samples, 50B2O3-10K2O-40Li2O (mol%) glass possesses larger ΣR (=0.11755 cm−1), whereas 25B2O3-37.5Si2O-37.5Gd2O3 (mol%) glass shows large σT (=646.171 cm−1) and SP for thermal neutrons at minimal thickness, indicating the included Gd2O3’s positive effect as element Gd has a high neutron absorption capacity. Employing the Phy-X/PSD program and MCNPX code, μ/ρ (mass attenuation coefficient) of all selected glasses is calculated for a γ-ray energy span of 0.015 – 15 MeV. Gd2O3 or Bi2O3 addition improved μ/ρ, and such increment is significant at low energies owing to PEA (photoelectric absorption) dominance and Gd or Bi K-edges. Also, for 15B2O3-10ZnO-5Li2O-70Bi2O3 (mol%) glass, μ/ρ has been derived by the WinXCOM program and FLUKA, Geant4, and PHITS codes, and a good accord between such simulated and theoretical μ/ρ outcomes is noticed following the calculated relative differences. Next, linear attenuation coefficient, effective atomic number and electron density, MFP (mean free path), TVL (tenth-value layer), HVL (half-value layer), and RPE (radiation protection efficiency) have also been evaluated. Comparatively, at 1.25, 0.662, and 0.2 MeV energies, 15B2O3-10ZnO-5Li2O-70Bi2O3 (mol%) sample possesses lower MFP and HVL than five SCHOTT AG commercial glass shields. Approximated RPE results affirmed all Gd2O3-SiO2-B2O3 and Bi2O3-Li2O-ZnO-B2O3 samples’ potent absorption (almost 100%) ability for lower energy γ-rays. Moreover, equivalent atomic number, and by geometric progression fitting process, within energy 15 keV–15 MeV extent for ten different penetration depths at 1–40 mfp span buildup factors have been assessed. 15B2O3-10ZnO-5Li2O-70Bi2O3 (mol%) glass exhibits better gamma-ray shielding effectiveness in all chosen samples, specifying Bi2O3’s favorable impact. Changes in photon shielding factors were interpreted following pair production, Compton scattering, and PEA processes. Later, elastic (Young’s (Y), bulk (K), shear (S), and longitudinal (L)) moduli and Poisson’s ratio values have been calculated for all inspected glasses. BC (bond compression) and M-M (Makishima–Mackenzie) models were utilized for such elastic traits reckoning. All K, Y, S, and L values’ trends for binary B2O3-Li2O glasses were identical in both BC and M-M models, and Kbc was found to be raised from 73.63 to 89.89 GPa, while KM–M increased from 75.35 to 180.53 GPa accordingly when Li2O content improved from 9.6 to 39.9 mol% in the chemical composition.

The current study aims to explore the shielding properties of multi-component borate-based glass series. Seven glass-samples with composition of (80-y)H3BO3–10ZnO–10Na2O–yBaO where (y = 0, 5, 10, 15, 20, 25 and 30 mol.%) were synthesized by melt-quench method. Various shielding features for photons, neutrons, and protons were determined for all prepared samples. XCOM, Phy-X program, and SRIM code were performed to determine and explain several shielding properties such as equivalent atomic number, exposure build-up factor, specific gamma-ray constants, effective removal cross-section (ΣR), neutron scattering and absorption, Mass Stopping Power (MSP) and projected range. The energy ranges for photons and protons were 0.015–15 MeV and 0.01–10 MeV, respectively. The mass attenuation coefficient (μ/ρ) was also determined experimentally by utilizing two radioactive sources (166Ho and 137Cs). Consistent results were obtained between experimental and XCOM values in determining μ/ρ of the new glasses. The addition of BaO to the glass matrix led to enhance the μ/ρ and specific gamma-ray constants of glasses. Whereas the remarkable reductions in ΣR, MSP, and projected range values were reported with increasing BaO concentrations. The acquired results nominate the use of these glasses in different radiation shielding purposes.

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.

For five B2O3–Bi2O3 glasses, detailedly, γ, neutron, & proton, alpha, and electron (charged particles) shielding efficacies were assessed in this work. The crucial photon attenuating (interaction probabilities) parameter i.e., mass attenuation coefficient (μ/ρ) was calculated by Phy-X/PSD software and procured μ/ρ results have been verified through MCNPX, Geant4, & FLUKA codes μ/ρ findings from which a quality unanimity among them was noticed over an energy range of 15 KeV–15 MeV. Following μ/ρ & linear attenuation coefficient (μ) outcomes, Zeff, Neff, HVL, TVL, and MFP have been reckoned and found that all μ/ρ, Zeff, Neff, HVL, TVL, & MFP highly rest on glass chemical contents & photon energy. Zeq and by applying geometric progression (G‒P) fitting parameters (a, b, c, d, & Xk coefficients) EBFs & EABFs were appraised at ten specific penetration depths up to 40 mfp, at energy range of 0.015–15 MeV. The inferred RPE quantities confirmed all chosen glasses quintessential absorption competence for lower energy γ-rays. Utilizing SRIM code the mass stopping powers (MSPs) & projected ranges (PRs) for protons ((ΨP)&(ΦP)) and alpha particles (ΨA)&(ΦA), and with the help of ESTAR database, electron MSP (ΨE) & continuous slowing down approximation (CSDA) ranges for electrons have been approximated at 0.015–15 MeV KE. The fast neutron removal cross-sections (ΣR) were estimated and obtained ΣR was diversified at 0.10978–0.12144 cm−1 range relying on Bi2O3 inclusion in glasses. Based on all acquired outputs, 57.5B2O3-42.5Bi2O3 (mol%) glass possesses superior attenuation capacity for γ-rays and fast neutrons as well as charged particles.

For B2O3-Bi2O3-BaO glass system, γ, proton, alpha, electron, and neutron radiation shielding aspects were examined. Adopting Phy-X/PSD software, mass attenuation coefficients (μ/ρ) have been derived, and such μ/ρ quantities are in good unanimity with evaluated FLUKA, Geant4, and MCNPX codes corresponding μ/ρ end products. Equivalent atomic number and up to 40 mfp ‘buildup factors’ (utilizing G–P fitting procedure) were reckoned at ten distinct penetration depths. Deduced radiation protection efficiency values validated all glasses’ laudable absorption potential for the minimal energy photons. At 15–15 × 103 KeV kinetic energy range, alpha particle and proton mass stopping powers and projected ranges by SRIM code including electron mass stopping power using ESTAR database were evaluated. For fast neutrons, the calculated macroscopic effective removal cross-section (ΣR) reveals that 25B2O3-70Bi2O3-5BaO (mol%) sample owns proportionately larger ΣR (=0.1206 cm–1). 70B2O3-15Bi2O3-15BaO (mol%) glass exhibits the largest total cross-section for thermal neutron absorption. Further, various physical features and elastic (Young’s, bulk, shear, and longitudinal) moduli and Poisson’s ratio values were derived for all samples. Both BC (bond compression) and M-M (Makishima–Mackenzie) models have been utilized for elastic aspects evaluation, and such features are altered considerably with Bi2O3 increment in the studied glasses. By BC and M-M models, obtained Poisson’s ratio is varied at 0.2434 – 0.2749 and 0.2384 – 0.2826 ranges respectively.

For five Ga2O3-Bi2O3-B2O3 composition glasses for improved Bi2O3 content at 25 to 65 mol% (10% continuously each time) at a fixed 10 mol% Ga2O3 amount, distinct physical and mechanical aspects and nuclear radiation attenuation factors were investigated. Increased Λ (optical basicity) values with a gradual Bi2O3 addition indicate studied samples’ improving basic character. Applying BC (bond compression) model key mechanical traits such as Ybc (Young’s modulus), Kbc (bulk modulus), S (shear modulus), L (longitudinal modulus), and σ (Poisson’s ratio) are evaluated where in all glasses 10Ga2O3-65Bi2O3-25B2O3 (mol%) sample exhibits superior elastic moduli. Enhanced Bi2O3 causes for compactness of the gallium borate network as ǹc (average cross-link density) improves from 2.3 to 3.4 indicating increased rigidity of glasses. Later, PHITS, FLUKA, and MCNPX codes are wielded to derive μ/ρ (mass attenuation coefficient) of all selected samples for photons having energy ranging from 15 KeV to 15 MeV. Simulated μ/ρ quantities exactitude is tested via Phy-X/PSD and WinXCOM programs’ μ/ρ results and identified a fairly good harmony among them. With photon energy, MFP (mean free path), TVL (tenth-value layer), and HVL (half-value layer) values variations show a similar tendency and against the trend which noticed for μ/ρ and μ (linear attenuation coefficient) values. 10Ga2O3-65Bi2O3-25B2O3 (mol%) sample’s MFP and HVL are correlated with five commercial γ-ray glass shields’ respective values at 1.25 MeV, 0.662 MeV (137Cs), and 0.2 MeV energies. Further, Zeq (equivalent atomic number) and using G–P (geometric progression) fitting approach for ten individual PDs (penetration depths) within 1–40 mfp range at 15 – 15 × 103 KeV energy region BUFs (buildup factors) were estimated. Attained RPE (radiation protection efficiency) findings attest all chosen Ga2O3-Bi2O3-B2O3 glasses’ competent absorption capacity for lower energy photons. Next, α-particles and protons MSPs (mass stopping powers), i.e. ΨA and ΨP and PRs (projected ranges), i.e. ΦA and ΦP by utilizing SRIM code as well as for electrons MSPs (ΨE) and CSDA (continuous slowing‐down approximation) ranges by ESTAR database have been calculated within 15–15 × 103 KeV KE (kinetic energy) range. Also, ΣR (fast neutron removal cross-section) and for 0.253 × 10–4 KeV energy neutrons σT (total cross-section) and SP (shielding percentage) values were approximated. With Bi2O3 addition, realized ΣR is changed at 0.1161–0.1213 cm−1 extent. For thermal neutrons absorption, 10Ga2O3-25Bi2O3-65B2O3 (mol%) glass shows larger σT (=17.534 cm−1) and at any considered thickness higher SP whereas 10Ga2O3-65Bi2O3-25B2O3 (mol%) (lead-free) glass has better attenuating features for photons affirming the incorporated Bi2O3 favorable effect.

Against photon energies extending from 0.015 to 15 MeV, MCNPX, FLUKA and PHITS codes are operated to simulate mass attenuation coefficients (μ/ρ) for a total of ten B2O3-Bi2O3-Li2O glass compositions with added Bi2O3 amount from 10 to 55 mol% (5 mol% growth gradually) as a substitute for total (B2O3 + Li2O) mol% content. All the computed μ/ρ values correctness is examined by Py-MLBUF and WinXCOM programs’ μ/ρ outcomes and we found a good agreement among them. 55Bi2O3-35B2O3-10Li2O (mol%) glass half-value layer (HVL) and mean free path (MFP) quantities are compared with distinct commercial γ-ray attenuating glasses, alloys, polymers, concretes and lead and ceramics corresponding values. Next, equivalent atomic numbers (Zeq) and by employing geometric progression (G–P) fitting method at 1–40 mfp PDs (penetration depths), at 0.015–15 MeV energy range ‘buildup factors’ were calculated. At all chosen twenty-five energies derived radiation protection efficiency (RPE) results assured investigated samples exemplary competence for low energy photons absorption. Applying SRIM codes ΨP and ΦP and ΨA and ΦA (mass stopping powers (MSPs) and projected ranges (PRs) for protons and α-particles), and making use of ESTAR database ΨE (electron MSP) and continuous slowing‐down approximation (CSDA) range for electrons are determined at KE (kinetic energy) range of 0.015–15 MeV. Moreover, fast neutron removal cross-sections (ΣR), for 0.0253 eV energy neutrons absorption cross-sections have been estimated. Deduced ΣR was altered at 0.1105–0.1205 cm−1 range with Bi2O3 inclusion in studied samples. 10Bi2O3-70B2O3-20Li2O (mol%) glass has greater total cross-section (=23.251 cm−1) for thermal neutrons absorption while 55Bi2O3-35B2O3-10Li2O (mol%) sample exhibits quality shielding factors for photons and fast neutrons confirming the included Bi2O3 positive impact. Along with nuclear attenuation features various physical and mechanical aspects are also inspected. Derived Vm (molar volume), OPD (oxygen packing density), Vo (oxygen molar volume), Vt (packing density) and Gt (dissociation energy per unit volume) values indicated glasses rigidity. Following Makishima–Mackenzie's theoretical model primary mechanical features like Y, K, S and L (Young's, bulk, shear and longitudinal modulus) and σ (Poisson's ratio) are evaluated where 10Bi2O3-70B2O3-20Li2O (mol%) glass shows better elastic moduli in all samples.

The current research article aims to study the radiation shielding competence of a newly developed PbO-B2O3-SeO2-Er2O3:Au2O3 glass ceramic. The concentrations of the constituent oxides were 40, 10, 49.5, and 0.5 mol % for PbO, B2O3, SeO2, and Er2O3, respectively. The studied ceramic specimens were denoted by EA0, EA25, EA50, EA75 and EA100, and their density values were 5.87, 5.92, 5.94, 6.09, and 6.10 g/cm3, respectively. The radiation shielding competence and photon buildup factors of the present ceramics were investigated under the Au2O3/SeO2 substitution with ratio up to 0.1 mol %. The obtained results reveal that the MAC values were reported with 0.233 cm2/g difference between the minimum and the maximum Au2O3 reinforced samples. The highest MAC values were reported for EA100 sample, which has the highest Au2O3 additive in its chemical structure. At 4 MeV photon energy, HVL values were reported as 3.2658 cm, 3.2352 cm, 3.2212 cm, 3.139 cm and 3.1309 cm for EA0, EA25, EA50, EA75 and EA100, respectively. Moreover, the highest values of EBF were observed for the EA100, and the lowest values of EBF were observed for EA0. Therefore, it can be concluded that the present ceramics possess high level shielding competence to use for various applications of gamma radiation.

MCNPX, Geant4 and FLUKA codes are employed to compute mass attenuation coefficients (μ/ρ) for 20Bi2O3-(80-x)B2O3-xPbO (x = 0, 20, 30, 40 and 60 mol%) glasses at 20, 30, 40 and 60 KeV, 133Ba (81, 161, 223, 276, 303, 356 and 384 keV), 57Co (122 and 136 KeV), 22Na (511 and 1275 keV), 137Cs (662 keV), 54Mn (835 keV), 60Co (1173 and 1333 keV) and 42K (1524 keV) photon peaks where 20, 30, 40 and 60 KeV energies are utilized for Mammography, Dental, General and Computed tomography (CT) scanning accordingly, in this study. All simulated μ/ρ outcomes accuracy was verified by WinXCOM and Phy-X/PSD programs’ μ/ρ findings and we noticed a satisfactory agreement among them. From μ/ρ and linear attenuation coefficient (μ) values effective atomic number (Zeff), effective electron density (Neff), half-value layer (HVL), tenth-value layer (TVL) and mean free path (MFP) have been determined. 20Bi2O3-20B2O3-60PbO (mol%) glass HVL and MFP have been compared with some commercial glasses, alloys, polymers, concretes and lead and ceramics corresponding values. Later equivalent atomic numbers (Zeq) and applying geometric progression (G–P) fitting method at 1 – 40 mfp penetration depths (PDs) at 0.015–15 MeV energy range exposure buildup factors (EBFs) and energy absorption buildup factors (EABFs) were estimated. At all selected twenty energies derived radiation protection efficiency (RPE) results confirmed studied samples’ excellent efficacy for low energy photons absorption. Moreover, applying SRIM codes mass stopping powers (MSPs) and projected ranges (PRs) for protons and α-particles and utilizing ESTAR database electron MSPs and continuous slowing down approximation (CSDA) range for electrons were determined at kinetic energy (KE) range of 0.015–15 MeV. Further fast neutron removal cross-sections (ΣR), for 0.0253 eV energy neutrons coherent and incoherent scattering cross-sections (σcs and σics), absorption cross-section (σA) and total cross-section (σT) quantities were evaluated. Derived ΣR was changed at 0.1166–0.123 cm−1 range depending on PbO addition in chosen samples. 20Bi2O3-80B2O3 (mol%) glass has larger σT (23.094 cm−1) in all studied samples for thermal neutron absorption while 20Bi2O3-20B2O3-60PbO (mol%) sample shows superior attenuation factors for photons and fast neutrons signifying included PbO positive effect.