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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.

From the useless municipal solid waste (MSW) ashes, CeO 2 , Gd 2 O 3 and CeO 2  + Gd 2 O 3 doped borosilicate glasses were organized via melting-quenching procedure. Various optical, structural, physical and radiation shielding parameters were examined towards the influence of 100 kGy of γ-radiation. UV–visible NIR spectra revealed UV peaks at 351, 348 and 370 nm corresponding to the trivalent states of Ce 3+ and Gd 3+ ions, while, photoluminescence (PL) spectra displayed asymmetric broad excitations of Ce 3+ and Gd 3+ ions due to 4f → 5d transitions, and emission intense bands at 412, 434, and 417 nm. CIE chromaticity shows that Gd 3+ ions increase the luminescence of Ce 3+ . FTIR absorption bands revealed an overlapping between tetrahedral groups of silicate (SiO 4 ), with trigonal (BO 3 ) and tetrahedral (BO 4 ) units of borate. The influence of 100 kGy obtains quite reduction in UV–visible NIR and PL peaks, large stability in FTIR and ESR spectra, and stability of thermal expansion coefficient (CTE) as well. The whole data revealed optical, structural and physical stability of glasses after irradiation besides an enhancement in microhardness owing to more structural compactness and high bonding connectivity. Radiation shielding parameters from Phy - X/PSD program showed higher values of mass (MAC) and linear attenuation coefficients (LAC), and effective atomic number (Z eff ) in the order of; glass Ce+Gd  > glass Ce  > glass Gd . Ce + Gd doped glass revealed also the lowest half value layer (HVL) comparing to other shielding commercial concretes. The study recommends the beneficial and economical use of the useless MSW ash to produce CeO 2 and/or Gd 2 O 3 borosilicate glasses with hopeful radiation shielding features.

Lithium bismuth silicate glasses with the composition of; 68% SiO2, 20% Bi2O3, 8% Li2O3, 4% Na2O doped with either 2% PbO, BaO or SrO (all in wt%) were studied to investigate some of their optical and electrical properties before and after different doses of gamma radiation. Density, oxygen packing density OPD, molar and specific volumes, optical UV absorption, optical energy gap, electrical conductivity and dielectric measurements were measured and discussed in this study regarding the effect of gamma radiation. The results showed that all glasses were more affected at the higher radiation dose (100 kGy) than the lower radiation dose (50 kGy) because of the creation of more defects and non- bridging oxygens NBOs at the higher dose. In spite of that, Pb2+ ions containing glass revealed better properties to resist gamma radiation than glasses containing either Ba2+ or Sr2+ ions because of its highly compacted structure and the low concentration of NBOs, defects or vacancies as well as the high polarizability of Pb2+ ions that plays an effective role in enhancing the glass optical and electrical properties.

Five undoped and transition metal doped lithium borate glasses, were prepared by melting annealing method at low temperature range (650–750 °C). X-ray diffractograms confirm the amorphous natures of the prepared glasses. Some of their properties such as density, Infrared absorption spectra (FTIR) and electrical conductivity have been studied before and after being subjected to gamma radiation. Optical UV absorbance and calculations of optical energy gap have been also studied on some selected glasses. The variation in density, electrical and spectroscopic parameters was discussed in terms of both valence state and ionic radius of each doped transition metal modifier. FTIR studies demonstrate that these glasses consist of BO 3 and BO 4 constructing groups with an obvious increase in their IR band intensities after irradiation with 20 kGy. The electrical properties of glasses were studied under the effect of both gamma radiation and temperature range from 298 to 473 K. A significant variation in electrical conductivity values was obvious when the temperature exceeds 413 K in the dose range from 5 to 20 kGy of gamma radiation.

A simple comparative study on the effect of doping barium borosilicate glasses by two different concentrations of TiO 2 is studied. Changes occurred in some of their physical properties due to subjecting to gamma radiation or heat treatment processes are also discussed. The measured properties are Density, Optical UV absorbance and transmittance, infrared absorption spectroscopy and scanning electron microscope. Ti ions can participate in the glassy network as effective modifier ions in the form of TiO 6 and TiO 4 octahedral groups. Titanium ions can exist in two valence states; the trivalent Ti 3+ and tetravalent Ti 4+ ions giving UV bands at 340 nm on the UV spectrum and at 400–480 nm after gamma irradiation. The main constituting groups BO 3 and BO 4 units give IR bands at 1250–1500 and 800–1200 cm −1 , respectively. In Ti-doped glasses, vibrational bands of SiO 4 , TiO 4 or (Si–O–Ti) vibrations are detected at 600–800 cm −1 . Heat treatment process at 525 °C for 6 h gives more ordered glassy structures with good properties; higher density, lower UV absorbance and higher transmittance, on the contrary, the effect of radiation that weakens the glassy structure and creates more non-bridging oxygens NBOs.

Municipal solid waste is used as a raw material for the production of borosilicate glasses by melting annealing technique. Many chemical and physical measurements are studied to test their possibility in the immobilization of radioactive wastes. The results show good behaviors against gamma radiation doses such as suitable density and microhardness values, stable behaviors towards low and high doses of gamma radiation indicated by IR and EPR techniques. As well as good chemical durability in H 2 O and NaOH leaching solutions. The network structure of borosilicate glasses consists of tetrahedral silicate units SiO 4 and the triangle BO 3 or tetrahedral BO 4 groups which strengthen the structure of glasses and enhance their desired properties for achieving the goal of immobilizing nuclear wastes.

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.

This work aims to investigate the effect of CeO 2 addition on structural, optical, and radiation shielding properties of B 2 O 3 –Na 2 O–SrO glass system. The XRD patterns of the glasses showed the amorphous nature of the glass. The FTIR spectra revealed that the CeO 2 addition promotes the transformation of the trigonal BO 3 to tetrahedral BO 4 units. Further, the energy gap decreased from 3.29 to 2.68 eV with the Ce content increasing. It is noticed that the dispersion parameters decreased by increasing the content of CeO 2 in BNSC glass. Also, the mass attenuation coefficient displayed a gradual decrease with the increment in energy. Further, the mean free path and half-value layer values decreased with the increasing amount of the CeO 2 . Furthermore, a good agreement between experimental and theoretical interpretations via Phy-X/PSD software was observed. Overall, the results revealed that the CeO 2 addition in glass samples makes them suitable for radiation protection utilizations.

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.

Three glass systems of Cu2+ ions doped lithium-borate with the composition of 56B2O3 + 25Li2O + 10Na2O + 5CaO + 2SrO + 2Al2O3 + 0.5TeO2 + xCuO, where x = 0.0, 0.2, and 0.3 wt% are synthesized by the conventional melt quenching method. X-ray diffraction (XRD) studies, Fourier transform infrared (FTIR) spectroscopy, electron spin resonance (ESR) spectroscopy, physical properties and ionizing radiation shielding performance of the prepared Cu2+-glasses have been investigated. All prepared Cu2+-glasses are in an amorphous structure nature. The density increases from 2.4379 to 2.4597 g.cm−3 as the Cu2+ ions content increased from 0.0 to 0.3 wt%. The FTIR spectra reveal four basic active areas in the IR spectra region (400–4000 cm−1). FTIR absorption spectra of glasses after irradiation with 10 kGy show that some of BO3 triangles are converted into BO4 groups. The ESR spectra for the investigated glasses exhibit highest intensity of the signal at the highest irradiation dose of 10 kGy. Linear attenuations coefficients (LACs) of the investigated glasses were arranged in order: (Cu0.0)LAC < (Cu0.2)LAC < (Cu0.3)LAC. Half-value layers (HVLs) values were found 0.088, 0.085, 0.083 cm, and 15.54, 15.43, 15.32 cm for Cu0.0, Cu0.2, and Cu0.3 at 0.015 and 15 MeV, respectively. MFPs arranged from 0.128 to 22.419 cm, and from 0.12 to 22.119 cm for Cu0.0–Cu0.3 at 0.015 and 15 MeV, respectively. For Cu0.3 glass, the transmission factor for gamma photon with energy 0.05 MeV decreased in order 63.53, 40.36, and 6.57% with increasing the glass thickness between 0.5, 1, and 3 cm, respectively. Finally, the results concluded that the 0.3 wt% CuO glass is considered as the best shield for gamma radiation among the other prepared glasses.