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Three borate glasses of 50, 35, and 15 mol% PbO-doped Ce, Sb, or Mn ions were fabricated via the melting-annealing procedure. Their structural features were inspected before and after 250 kGy of gamma irradiation using FTIR and ESR techniques. The spectra of the ESR and FTIR vibrational bands remain constant, with a minor reduction in N4 and an enhancement in density values after irradiation, indicating the large structural stability and glass compactness. Many radiation shielding parameters were studied, such as gamma dose rate (µSv/h), dose transmission %, lifetime cancer risk %, macroscopic effective removal cross-section (∑ R ), mass stopping power, and projected range values ​​were considered for protons particles by SRIM Monte Carlo simulation code and ESTAR program. The whole data reveals the high radiation shielding efficiency of the glasses compared to other standard shields to be used as glass immobilizers for radioactive wastes or storage containers, e.g., for nuclear medicine units in hospitals.

Samples of copper-modified bioactive borate glasses were synthesized and their radiation shielding properties including gamma-ray and neutron radiation shielding were investigated. Further, the glasses’ mass attenuation coefficients were measured with a NaI(Tl) detector while their gamma-ray shielding parameters were estimated using Phy-X/PSD program. Free-radical densities were measured via electron spin resonance to estimate the absorbed doses during accidental irradiation. The extensive reduction of the dose detection threshold (2 Gy) required the estimation of the signal of the non-irradiated sample. In addition, the effects of applied microwave power and absorbed dose on synthesized samples were studied. Finally, the thermal annealing of the emerging peaks, which were due to the irradiation signal-to-noise ratio and energy dependence, was studied to estimate the stabilities of such peaks. This modified material is recommended to detect and monitor the gamma-radiation dose because of its good dosimetric properties. Finally, regarding the presence of the two borate groups, triangular and the tetrahedrally coordinated, in their definite and typical wavenumbers, the FTIR spectra displayed simplified vibrations that were close to those of many bioglasses. This paper provides complementary results for the author's previous research examining this glass for low photon dose measurements using luminescence characteristics.

Ce/Sb/Mn different borate glass systems based PbO in concentrations of 50, 35, and 15 mol%, respectively, were prepared by the melting–annealing method. Wide chemical, structural, and radiation shielding characterizations were studied before and after 120 kGy of gamma radiation to test the possible use of glasses for immobilizing radioactive wastes. The results showed suitable density values ranging from 3.34 to 5.30 g/cm 3 increased by irradiation. FTIR spectra revealed high structural stability against irradiation correlated to the trigonal BO 3 , tetrahedral BO 4 groups, high polarizable Pb 2+ ions, and the doped metal ions. Unexpectedly, the chemical durability after in situ leaching process in H 2 O, 0.1 N HCl, and 0.1 N NaOH for ~ 3 months revealed clear improving after irradiation e.g., enhanced by ~ 25% for Ce-lead borate glass. Scanning electron microscope (SEM) images of the glass surfaces revealed more smooth and homogenous surfaces after irradiation. Shielding parameters by Monte Carlo code (MCNP5) and Phy-X/PSD software were studied, e.g., mass and linear attenuation coefficients (MAC and LAC), effective atomic number ( Z eff ), radiation protection efficiency (RPE%), half and tenth value layers (HVL and TVL), and heaviness%. Comparing the shielding behavior of the three glasses revealed that Ce-lead borate glass has the highest values of LAC, MAC, Z eff , heaviness%, and RPE% and the lowest values of HVL, TVL, and MFP, referring to the best shielding efficiency. The whole study indicates the desired properties of glasses as immobilizers or containers for radioactive wastes, e.g., nuclear medicine units in hospitals, especially lead borate glass doped Ce ions. Graphical Abstract

Changes in optical properties transparency of pure and cobalt oxide (CoO)-doped lithium borate glasses have been investigated for fresh and γ-irradiated samples. These changes either in the transparency or color due to the variation of Co concentration or γ-irradiation doses indicated changes occurred inside the glass matrix. The ability of this glass to shield gamma ray, neutron, electrons, and protons was also examined. The calculations of optical band gap values showed a decrease, with the increase in CoO concentration, while the refractive index increased. Mass attenuation coefficient (MAC) of glasses was measured at 662, 1173, 1275 and 1333 keV energies by utilizing NaI(Tl) detector; also, theoretically by using Phy-X/PSD program derivative gamma shielding parameters have been studied. It was found that an increase in CoO % makes increment of gamma attenuation. Moreover, adding CoO improves neutron absorption due to the bigger cross section of Co atoms. Charged particles as (proton and electron); glass samples give good results at 10 keV‒10 MeV kinetic energy range computed by SRIM code. This paper provides complementary results to the authors of previous research studies that examined this glass as an electron beam irradiation dosimeter.

Commercial window glass (CWG) is studied for application as a bandpass filter, dosimetric system, and for shielding low-gamma ( γ ) energy. To evaluate its dosimetric characteristics, optical transmission ( T %) and thermoluminescence (TL) were measured, dosimetric features were determined, and the impact of CoO on the observed properties is discussed in detail. Transmission spectra before and after irradiation with γ-irradiation (1, 5, 10, and 20 kGy) were measured over a wavelength range of 200–900 nm. Differences in transmission bands at ~ 380, 530, 590, and ~ 645 nm were observed as a function of irradiation level, designating the usefulness of CWG as a bandpass filter. A broad TL glow peak at 210 °C was also observed before and after irradiation. The increase in TL intensity after irradiation suggests that additional luminescence trapping centers were created when the CWG was subjected to different irradiation doses. Additionally, the simple glow curve, linear TL response to a range of γ -doses, and a fading investigation of the CWG reveal its absorbed dose repeatability for periods of up to 32 days post-exposure. These results make CWG a good material for use in TL dosimetry. The linear attenuation coefficients were also experimentally and theoretically determined by γ -beam spectroscopy and the WinXCOM program, respectively. Gamma shielding parameters were also calculated for different γ energies. The obtained results demonstrate that the CWG is suitable for use as a protective shield against low-energy gamma rays (less than 60 keV). Furthermore, the fast neutron removal cross section was determined to be 0.087 cm −1 .

Fluorophosphates glass systems with a composition of 70(P 2 O 5 )–20(LiF)–10(AlF 3 )– x (Sm 2 O 3 ): x  = 0.0, 0.2, 0.5, 1, and 3 mol% have been synthesized and characterized in relation to their shielding, optical, and physical properties. The optical transmittance in UV–visible near IR region displays high transparency of the glasses and strong transmission bands with good stability after gamma irradiation. Studying thermal properties of the glasses by DTA and many of their physical parameters e.g. optical energy gap E opt , refractive index ( n ), optical transmittance coefficient ( T ), reflection loss ( R L ), optical electronegativity ( X ) as well as dielectric constants, provides acceptable thermal and physical stability of the glasses. Gamma, neutron, alpha and proton radiation shielding perspectives have been also inspected comprehensively by a simulated model using Monte Carlo code MCNP5. Adopting Phy-X/PSD software, μ m revealed great compliance with MCNP5. By applying ( μ / ρ ) output for gamma at different energies, Z eff , N eff , HVL, and TVL have been also estimated. All the data approve the exemplary absorption ability of the glasses for the lower energy photons as confirmed by radiation transmission. Each increase in Sm 3+ mol% makes an increment of thermal neutron and gamma attenuation, providing the protecting properties of the glasses against gamma, neutron, proton and alpha particles. Furthermore, alpha mass (ΨA) and proton stopping powers (ΨP) as well as alpha (ΦA) and proton projected ranges (ΦP) were computed by SRIM code for all glasses at 10 keV–10 meV kinetic energy range for estimating the glasses shielding properties.

Radiation safety and protection is a subject of major concern for all communities because of the biological damage caused by different radiation sources. Therefore, the purpose of this study is aimed to synthesize two different thin films from a newly synthesized N-Al 2 O 3 @Pb(II)-2,4-DiNA nanocomposite which was prepared by the direct chemical coupling of nano-aluminum oxide (N-Al 2 O 3 ) with Pb(II)-2,4-dinitroaniline complex. The synthesized materials were characterized by FT-IR, thermogravimetric analysis (TGA), scanning electron microscope SEM, and elemental composition by energy-dispersive X-ray (EDX). The two thin films were assembled by the encapsulation of N-Al 2 O 3 @Pb(II)-2,4-DiNAnanocompositeinto hydrolyzed polyurethane and hydrolyzed polyvinyl chloride. Electron spin resonance (ESR) measurements have been used to investigate the newly prepared nanocomposite and thin films before and after gamma irradiation. Gamma spectroscopy, Phy-X software, and SRIM (stopping and range of ions in matter) Monte Carlo simulation code are aimed to apply and investigate radiation shielding efficiency of films for gamma/x-ray, protons, alpha, and thermal neutrons. The gamma shielding characteristics, mass stopping power (MSP), and range for both proton (H-ions) and alpha (He-ions) were also calculated. In addition, the SRIM code’s subroutine TRIM was used to predict the damage production and atomic displacements per atom (dpa) caused by the interaction of high-energy H-ions (proton) and He-ions (alpha) with the studied samples. The data obtained the good radiation shielding effect of the prepared thin films and their possible use as radiation shielding materials for X-rays and low gamma energy.

The integration of IoT technologies with smart logistics operations has opened unprecedented avenues for optimizing energy consumption in warehouse facilities. Accurate forecasting of electricity load is a key factor in cost reduction, operational efficiency, and sustainable energy management. This study presents an Enhanced Integrated Load Forecasting System (E-ILFS) that synergizes metaheuristic optimization with deep learning architectures of higher order for superior electricity load forecasting in dynamic logistics environments. Building on the foundational ILFS framework, our enhanced approach integrates Harris Hawks Optimization (HHO) for robust feature selection and an improved Residual Network (ResNet) enhanced with self-supervised learning (SSL) to more effectively capture complex, non-linear temporal patterns. Finally, comprehensive experimental evaluation on a real-world IoT-driven logistics dataset demonstrates that E-ILFS achieves state-of-the-art performance with an R² score of 0.8745, MAE of 23.59, and MAPE of 3.22%, representing a significant 12.51% improvement in R² over baseline models. In fact, the proposed system provides a practical and scalable solution for real-world logistics operations.

SURF is one of the most robust local invariant feature descriptors. SURF is implemented mainly for gray images. However, color presents important information in the object description and matching tasks as it clearly in the human vision system. Many objects can be unmatched if their color contents are ignored. To overcome this drawback this paper proposed a method CSURF (Color SURF) that combines features of Red, Green and blue layers to detect color objects. It edits matched process of SURF to be more efficient with color space. Experimental results show that CSURF is more precious than traditional SURF and CSURF invariant to RGB color space

Based on municipal solid waste (MSW) ash as a main raw material, three novel borosilicate glasses with the composition of 70 waste + 20 borax + 10 Na 2 O + x ZrO 2 , where x = 0, 0.1 or 0.3 (wt. %),were prepared by the traditional melting-annealing technique. The prepared glasses were analyzed by EDX analysis, revealing the rich compositions of the prepared glasses correlated to the MSW ash used by 70 wt.% in preparing glasses. Some optical, chemical and radiation shielding properties of the prepared glasses were investigated. Either Zr addition or 80 kGy of gamma radiation revealed improvement of the glasses optical transmittance and chemical durability in neutral dis H 2 O, alkaline 0.1 N NaOH and acidic 0.1 N HCl leaching media for 70 days. Electron spin resonance (ESR) revealed the same spectra before and after irradiation, referring to the prevention of free radical formation by irradiation. The shielding parameters were measured by the experimental gamma spectroscopy (NaI detector) and the theoretical Phy-X/PSD software e.g., linear attenuation coefficients (LAC) and the findings revealed high unanimity among them at photon energies 0.662, 1.173 and 1.333 MeV. Another shielding parameters were also studied e.g., mass attenuation coefficients (MAC), effective atomic number (Z eff ), effective electron density (N eff ) and effective conductivity (C eff ). Presence of various metal oxides and the host trigonal BO 3 and tetrahedral BO 4 and SiO 4 units, and ZrO 2 provide the glasses compactness and effectual stability against ionizing irradiation. The prepared borosilicate glasses have highly strong and compacted structures that can inhibit the passage of radiation photons, because of the variety of many glass network formers, intermediates and modifiers present in the used waste ash. The results indicate the highly economic benefit of the prepared glasses, where the useless MSW ash are used mainly by 70 wt.% to produce effective borosilicate glass systems for promising radiation shielding purposes, especially 0.3 Zr borosilicate glass that has the best radiation shielding properties.