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The sonication method was used to prepare a new set of CuO and CuO/Ag nanocomposites. The particle size was estimated using XRD and HR-TEM while the morphology of the nanoparticles was investigated with SEM. The average particle sizes of CuO and Ag falls in the 29.32–35.80 nm and 35.13–45.95 nm ranges, respectively. XRD declared that CuO has the space groups C 1 c 1 (9) and C 1 2/c 1 (15), while silver has space group F m -3 m (225). XPS analysis indicated the presence of Ag as Ag 0 and Cu as Cu 2+ . Nano-oxide and nanocomposites were used to synthesis CuO and CuO/Ag doped lithium–zinc borosilicate glass. Physical parameters of the glass samples were calculated including density, V m , V o , V m B , OPD, d B - B , n b , and N, R p , and R i depending on Ag and CuO mole fractions. The physical properties of glass indicated an increase in density and an initial expansion in glass structural network with the addition of silver metal due to its larger size followed by a compression as its molar ratio increase due to its higher C no . XRD measurements were reported for the glass samples doped with nanoparticles, proving the amorphous phase. ESR measurements were determined for all glass samples to detect the nature of the doped nanoparticles when incorporated inside a glassy matrix where CuO was found as tetragonal in octahedral sites and silver can be transformed after melting inside the glass matrix into Ag + to form more stable Ag y x + clusters.The fabricated sample of CuAgB-4 with significant nano silver doping (7.32% mol) has the maximum LAc and effective atomic number. Nano silver content increases the γ -RdSg in the lithium–zinc borosilicate glasses.

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.

The preparation of materials with high attenuation performance is one of the major issues in the radiation shielding applications. This study is based on the investigation of gamma-shielding performances of various polyester composites reinforced with Zn. Utilizing gamma spectrometer based on HPGe detector, the mass attenuation coefficient ( μ / ρ ) of the present composites was measured at various photon energies between 59.5–1408 keV. The obtained experimental data were confirmed with those of MCNPX code as well as XCOM program. It is found that the attenuation coefficient values of the studied composites are in good agreement with the results of other approaches at the investigated energies. The best photon-shielding effectiveness was observed in the composite tagged with Zn (10%). The shielding characteristics of composite enhances with the addition of Zn as filler.

In the current work, polymethyl methacrylate (PMMA)/ x wt % ZnMoO 4 polymers were constructed to utilize in energy storage and radiation shielding fields. The structure, morphological, dielectric and radiation shielding aspects of PMMA/ x wt % ZnMoO 4 polymers were explored. X-ray diffraction (XRD) technique was employed to determine the structure and crystallite size of ZnMoO 4 filler sample. XRD and SEM techniques were employed to inspect the crystallinity and morphology of PMMA/xwt%ZnMoO 4 polymers. Using 2 wt% ZnMoO 4 filler enhanced the polymer's energy storage capacity. The energy density attained its maximum values as PMMA doped with 3 wt% ZnMoO 4 . Polymer with 2 wt % ZnMoO 4 has the highest AC conductivity. Argand plots were used to discover the impact of loading ratio on the capacity of the host polymer. The linear attenuation coefficient (LAC) and mass attenuation coefficient (MAC) values at lower photon energies were increased up to 6.446 cm −1 and 4.821 cm 2 /g, respectively, as the polymer doped with 5 wt% ZnMoO 4 . The effect of doping on the half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number ( Z eff ), effective electron density ( N eff ), effective conductivity ( C eff ), Exposure Buildup Factor (EBF) or the Energy Absorption Buildup Factor (EABF) were explored. A higher Fast neutron removal cross-section (FNRCS) value in the loaded samples relative to the pure sample.

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 .

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.

The optical and radiation shielding of PVA have been enhanced through embedding with ZnO/CuO/SWCNT (ZCS) nanocomposites. ZCS polymeric nanocomposites (PNCs) were prepared with the solution casting method. Scanning electron, optical microscopy and FT-IR procedures were performed to examine the surfaces’ morphology and structures’ modifications. UV–visible measurements were carried out to investigate the linear/nonlinear optical properties. The optical investigations show significant alterations in the optical parameters of PVA due to ZCS embedding. The UV–visible analysis shows that the optical parameters, including the transmittance, energy bandgap, refractive index, dielectric constants and optical conductivity of PVA, are tuned through ZCS embedding. The direct and indirect bandgap of PVA shrank from 5.42 eV and 4.99 eV (neat PVA) to 3.20 eV and 2.26 eV (10 wt.% ZCS PNCs). The nonlinear optical (NLO) constants (first order susceptibility (χ(1)), third susceptibility (χ(3)) and refractive index (n2)) of PVA were improved. Phy-X/PSD software was used to investigate the radiation shielding parameters of all samples. The linear attenuation coefficient (LAC), mean free path (MFP), half value layer (HVL), tenth value layer (TVL) and effective atomic number (Zeff) of PVA were enhanced through ZCS embedding. It is found that the mass attenuation coefficient (MAC) of the neat PVA increased from 1.14 cm2/g to 7.96 cm2/g at 0.015 MeV. The HVL of PVA decreased from 30.2 cm to 20.6 cm, the TVL decreased from 100.3 cm to 68.5 cm and the MFP decreased from 43.6 cm to 29.8 cm upon embedding 10 wt.% of ZCS NCs at 15 MeV. The samples’ exposure buildup factor (EBF) and energy absorption buildup factor (EABF) in the photon energy range from 0.015 MeV to 15 MeV at 0.5 to 40 MFP values. This study proves that ZCS PNCs are advantageous for applications in optical and radiation shielding fields.

This study aimed to perform an investigation for the potential implementation of bismuth silicate glasses as novel shield equipment instead of ordinary shields in nuclear medicine facilities. Accordingly, a group of Bi2O3 reinforced silicate glass system were investigated and compared with ordinary shields in terms of their gamma-ray attenuation properties in diagnostic nuclear medicine radioisotope energies emitted from 99mTc, 111In, 67Ga, 123I, 131I, 81mKr, 201Tl, 133Xe. Mass attenuation coefficient (μm) results for glass samples were calculated comparatively with the XCOM program and MCNPX code. The gamma-ray attenuation parameters such as half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Zeff) were obtained in the diagnostic gamma ray energy range from 75 to 336 keV. To confirm the attenuation performance of superior sample, obtained results were extensively compared with ordinary shielding materials. According to the results obtained, BISI6 glass sample with the highest Bi2O3 additive has an excellent gamma-ray protection.

Dysprosium oxide-doped glasses with a composition of 60B 2 O 3 -10Sb 2 O 3 -10Al 2 O 3 -10NaF-(10-x) LiF-xDy 2 O 3 (x = 0.1,0.5, 1.0,1.5,2.0,2.5 mol%) were prepared using a conventional melt-quenching technique. The glasses were characterized through various analytical investigations, including X-ray diffraction (XRD), Fourier transform infrared (FTIR) spectroscopy, refractive index, density, optical absorption, excitation, photoluminescence (PL) studies, decay measurements and radiation shielding parameters. The XRD and FT-IR confirms the glassy nature and functional groups present in the titled glass. The absorption spectra were used to determine the oscillator strength of the Dy 3+ absorption transitions as well as the bond created with the O −2 ion in the titled glass network. The degree of the suitability of developed glasses for lasing applications was demonstrated by radiative parameters determined using Judd–Ofelt theory. In the prepared glass samples, the optical bandgap measurements indicate the presence of non-bridging oxygen (NBOs), localization of charges and donor centers in the titled glasses. Due to the de-excitation of 4 F 9/2 to the corresponding 6 H 15/2 , 6 H 13/2 and 6 H 11/2 states, the PL emission spectrum shows two main strong emissions at blue(480nm), yellow (575nm) and one less emission at red (663nm). The CIE coordinates determined using PL emission spectra reveal the coordinates that are falling within the white light region. Various shielding parameters such as mass attenuation coefficient, mean free path, effective atomic number were estimated to understand the radiative shielding nature of the titled glasses. Within the addition of Dy 2 O 3 , it was found that the shielding parameters values of the titled glass samples are increasing. The Mass Attenuation Coefficient, Half Value Layer and Mean Free Path of the as prepared glasses has been compared with different types of concretes to understand the shielding effectiveness of prepared glass.