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We report the optical and experimental gamma-ray and neutron attenuation properties of tantalum pentoxide reinforced Bi2O3–TeO2–ZnO ternary glasses with a nominal composition of 10Bi2O3–70TeO2-(20-x)ZnO-xTa2O5 (where x = 0,2,4, and 6 mol%). Measurements of transmittance and absorbance spectra for all of the synthesized samples are performed with Analytik Jena Specord 210 plus device between the range of 190–1100 nm. Moreover, 133Ba and 241Am/Be sources are utilized for experimental gamma-ray and neutron attenuation studies of BTZT glasses. According to results, the absorption edge is consistently moved from 380 nm to 390 nm as a result of ZnO/Ta2O5 translocation. In addition to decrease in optical band gap values of glass series, the fact that doping the structure containing Ta2O5 is lead to an increase in Urbach energies. The obtained irregularity through an increasing Ta2O5 additive is also changed the overall nuclear radiation attenuation properties of the BTZT glasses. The gamma-ray attenuation properties are obviously enhanced within the energy range of 133Ba radioisotope. The attenuation properties against fast neutron emitted from 241Am/Be were significantly enhanced through increasing Ta2O5 contribution. It can be concluded that BTZT6 glass sample may be regarded as a beneficial glass composition for multifunctional applications. It can be also concluded that ZnO/Ta2O5 translocation in Bi2O3–TeO2–ZnO ternary glasses may be regarded as a monotonic tool where the neutron attenuation properties should be strengthened in addition to gamma attenuation properties.

The purpose of this comprehensive research is to observe the impact of scintillator crystal type on entire detection process. For this aim, MCNPX (version 2.6.0) is used for designing of a physical plastic scintillation detector available in our laboratory. The modelled detector structure is validated using previous studies in the literature. Next, different types of plastic scintillation crystals were assessed in the same geometry. Several fundamental detector properties are determined for six different plastic scintillation crystals. Additionally, the deposited energy quantities were computed using the MCNPX code. Although six scintillation crystals have comparable compositions, the findings clearly indicate that the crystal composed of PVT 80% + PPO 20% has superior counting and detecting characteristics when compared to the other crystals investigated. Moreover, it is observed that the highest deposited energy amount, which is a result of the highest collision number in the crystal volume, corresponds to a PVT 80% + PPO 20% crystal. Despite the fact that plastic detector crystals have similar chemical structures, this study found that performing advanced Monte Carlo simulations on the detection discrepancies within the structures can aid in the development of the most effective spectroscopy procedures by ensuring maximum efficiency prior to and during use.

Half Value Layer calculations theoretically need prior specification of linear attenuation calculations, since the HVL value is derived by dividing ln(2) by the linear attenuation coefficient. The purpose of this study was to establish a direct computational model for determining HVL, a vital parameter in nuclear radiation safety studies and shielding material design. Accordingly, a typical gamma-ray transmission setup has been modeled using MCNPX (version 2.4.0) general-purpose Monte Carlo code. The MCNPX code's INPUT file was designed with two detection locations for primary and secondary gamma-rays, as well as attenuator material between those detectors. Next, Half Value Layer values of some well-known gamma-ray shielding materials such as lead and ordinary concrete have been calculated throughout a broad gamma-ray energy range. The outcomes were then compared to data from the National Institute of Standards and Technology. The Half Value Layer values obtained from MCNPX were reported to be highly compatible with the HVL values obtained from the NIST standard database. Our results indicate that the developed INPUT file may be utilized for direct computations of Half Value Layer values for nuclear safety assessments as well as medical radiation applications. In conclusion, advanced simulation methods such as the Monte Carlo code are very powerful and useful instruments that should be considered for daily radiation safety measures. The modeled MCNPX input file will be provided to the scientific community upon reasonable request. © 2022 Korean Nuclear Society Princess Nourah Bint Abdulrahman University, PNU: PNURSP2022R149 This work was performed under Princess Nourah bint Abdulrahman University Researchers Supporting Project Number (PNURSP2022R149), Princess Nourah bunt Abdulrahman University, Riyadh, Saudi Arabia. The authors express their sincere gratitude to Princess Nourah bint Abdulrahman University.

We present synthesis and thorough characterization phases of newly developed 20P2O5·30TeO2.(50-x)ZnO.xCdO (x = 0, 2, 4, 6, 8, 10 mol%) glasses. Experimental gamma-ray and neutron transmission systems are used in terms of exploring the monotonic effects of increasing CdO reinforcement on behavioural changes of synthesized glasses through well-known melt-quenching method. A conventional gamma-ray setup along with a high purity germanium detector as well as 133Ba radioisotope is used for determination of attenuation coefficients. Glass shields are irradiated with a241Am/Be neutron source using the Canberra NP-100B BF3 gas proportional detector. The addition of 10% mole CdO to the basic glass composition had a significant favorable impact on the transition resistance to gamma and neutron radiation. In comparison to all available shielding materials, (except RS-520), the C10 sample demonstrated superior gamma-ray attenuation capabilities. According to results, C glasses generally exhibit superior neutron attenuation capabilities than conventional moderators. It can be concluded that C glass family may be considered as suitable gamma-shield and neutron moderator in different types of applications from research to medical radiation fields. © 2022 Elsevier Ltd and Techna Group S.r.l. 2-s2.0-85130343951

In this study, three heavy metal oxide glasses (A:46.0PbO-42.0Bi2O3-12.0Ga2O3, B:45.94PbO-42.66Bi2O3-10.0Ga2O3-1.4BaO, C:72.8PbO-17.0GeO2-10.2Ga2O3) were synthesized to determine their optical and gamma-ray shielding properties in terms of assessing their potential applications in medical and industrial radiation facilities. Glasses were synthesized using melt quenching method. The optical band gap energy is calculated by the absorption spectrum measured at room temperature. We found a large band at 500 nm that refers to Bi+ions and appears to samples A and B that contain Bi2O3 in their compositions. Optical band gap energies were reported as 2.014 ev, 2.055 eV and 2.430 eV for A, B and C samples, respectively. Next, fundamental gamma-ray parameters were also determined using MCNPX general Monte Carlo code and Phy-X/PSD in 0.15–15 MeV photon energy. Our findings clearly showed that the B sample, which includes the highest concentration of Bi2O3, has a considerable advantage in terms of gamma-ray attenuation. Moreover, the results also showed that sample B has significantly higher attenuation properties than shielding concretes and several glass shields. It can be concluded that Bi2O3 is a useful component for heavy metal oxide glasses in terms of improving gamma-ray shielding capabilities for radiation shielding applications. © 2022 Elsevier Ltd and Techna Group S.r.l. 2-s2.0-85123891851

We report the critical optical properties such as Average Visible Transmittance (AVT), colour, Color Rendering Index (CRI), and Correlated Color Temperature (CCT) of a multicomponent glass system with a nominal composition of 50TeO(2)–30B(2)O(3)-(20-x)Li(2)O-xCeO(2) (x = 0,0.5,1,2,3,4,5,10,15,20 mol%). Various advanced theoretical approaches as well as calculations are utilized in terms of determining the optical properties of studied glasses. The maximum transmittance and AVT values of the glass system exceeded 80% and 79.59%, respectively. The colour coordinates are found extremely near to D65 and the achromatic point without CeO(2) contribution. According to our results, the current system has a promising ability to be utilized for coloured window applications in terms of both AVT and colour with 2% CeO(2) doping. Our results showed that, the CeO(2) additive is able to move the glass colour straight into the red spectrum by shifting the transmittance spectrum to the long-wavelength portion of the visible spectrum. With 10% CeO(2) doping, opacity in the visible area and permeability in the NIR region are obtained, and the CCT value changes from 5002 K to 2560 K. It can be concluded that a filter system with modifiable NIR or red optical characteristics may be produced through the CeO(2) alterations in borotellurite glass systems.

Introduction: Graphene-based materials have gained increasing attention for use in radiation attenuation applications. In this study, pristine graphene nanoplatelet-containing (1, 3, 5, and 10 wt%) borate-based bioactive glass composites were prepared.Methods: Structural properties, Vickers microhardness, and gamma-ray radiation shielding properties of the fabricated composites were examined in detail.Results and Discussion: Results revealed that the inclusion of the graphene in the glass matrix led to a decrease in the bulk density of the glass-based composites from 2.41 to 2.31 g/cm3. Similarly, a decrease in Vickers hardness was obtained as the graphene concentration was increased due to a convoluted effect of the non-uniform distribution of graphene nanoplatelets in the bioactive glass matrix and the higher residual porosity. Vickers hardness of the bare and the 10 wt% graphene-containing bioactive glass discs were measured to be 5.03 ± 0.28 GPa and 1.87 ± 0.56 GPa, respectively. On the other hand, the incorporation of graphene starting from 3 wt% decreased the crack propagation after indentation which may be attributed to an increase in fracture toughness. In the study, fundamental gamma ray absorption properties of graphene-containing bioactive glasses were examined in the 0.015–15 MeV incident photon energy range. For this purpose, the Py-MLBUF code was employed to determine gamma ray absorption parameters. Results showed that linear attenuation coefficients of the glass-based composites decreased due to a decrease in the density of the samples. On the other hand, as graphene was incorporated into the bioactive glass structure, exposure buildup factor and energy absorption buildup factor values increased. The growing graphene ratio in the glass structure contributed negatively to the photon’s tendency to interact with the material.

Doping the glass structure with Bi2O3 `is known to increase structural stability, and to drastically alter physical parameters including density and molar volume. The goal of this work was to assess the nuclear radiation attenuation competences of several types of glasses based on the xBi2O3-(70x)B2O3-8BaO-16ZnO-5.5SiO2- 0.5Sb2O3 system. In order to determine the requisite gamma shielding parameters, as well as effective conductivity at 300 K and buildup factors, five different glasses with varied Bi2O3 concentration (i.e., from 10 mol.% to 30 mol.%) were examined thoroughly. These critical parameters were determined using the Phy-X/PSD program. In addition, factors such as half value layer (HVL), tenth value layer (TVL), and mean free path (mfp) were examined over a wide energy range of 0.015-15 MeV. The findings revealed that the amount of Bi2O3 reinforced in each sample is critical in determining the samples' shielding abilities. The linear attenuation coefficients (mu) and mass attenuation coefficient (mu m) values were reported in the highest level for the sample with the highest Bi2O3 content. For glass sample A5, the lowest mean free path, half value layer, and tenth value layer values were also reported. The effective conductivity and effective atomic number had an inverse relationship with photon energy, meaning that as energy increased, the effective conductivity and effective atomic number declined fast, especially in low-energy regions. The greatest values for both parameters were found in glass sample A5. Furthermore, the exposure buildup factor and energy absorption buildup factor values for glass sample A5 were the lowest. A5 glass sample with the chemical composition 30Bi2O3-(70 30) B2O3-8BaO-16ZnO-5.5SiO2- 0.5Sb2O3 and a density of 5.8391 g/ cm3 was found to have exceptional gamma-ray attenuation qualities, according to our findings. It can be concluded that the prospective attributes of Bi2O3-doped glass systems and associated glass compositions would be beneficial for scientific community in terms of providing a clearer view for some advanced applications of these glass types. WOS:000893639300004 Q1

The present work reports the physical, structural, elastic, optical, and radiation shielding studies on (80˗X)H3BO3+10TeO2+9.5Nb2O5+XBaO+0.5Sm2O3 (where X = 10, 20, 30, 40, 50 in wt%) glasses which is prepared by the melt quenching technique. The bending and stretching vibrations of the different compounds used are analyzed through FTIR instrumentation. The density and refractive indices are measured experimentally following Archimedes's principles and by using Abbe's refractometer, respectively. Various structural parameters are calculated to resolve the actual placement of atoms in the glass complex, which explains the compactness of the network. Elastic properties of the synthesized glasses are calculated to estimate the resistance of glass under stress. Additionally, the optical band gap is calculated, and the nature of bonds in the network is ionic compared to the covalent nature. Boron–Boron distance is the lowest for 50BNTBSm sample. The decrease in OPD content is linked with the decrease in the number of oxygen atoms, for 10BNTBSm and 50BNTBSm glasses, it is 289 and 209 oxygen atoms, respectively. Λth value is high for 10BNTBSm glass sample with the minimum BaO reinforcement. The Urbach's energy varies from 0.534 to 0.967 eV, corresponding to xBNTBSm samples indicating fewer defects in the glasses. Moreover, gamma-ray and fast neutron attenuation properties of xBNTBSm are determined and compared with numerous shielding materials such as concrete and other types of glasses. Results showed that replacing 40% of H3BO3 with BaO leads to a net improvement in gamma-ray attenuation properties. However, this situation was the opposite in the fast neutron absorption properties. A clear superiority of sample 50BNTBSm was also reported against the compared absorbent materials. It can be concluded that replacing 40% of H3BO3 with BaO would provide some significant improvements to Niobium Bariumtelluroborate glasses. WOS:000860344800007 Q1

We report the functional assessment of various rare-earth (RE) ion types on gamma-ray attenu- ation properties of GeO2-B2O3-P2O5-ZnO-Tb2O3-RE (where; RE=0; 1 %Ho, 1 %Pr, 1 %Er, 1 %Nd, 1 %Dy, 1 %Ce) magneto-optical glasses. The elemental fractions and densities of each glass sample were specified separately for the MCNPX Monte Carlo code. In addition to fundamental gamma absorption properties, Transmission Factors throughout a broad radioisotope energy range were measured. According to findings, Holmium (Ho) incorporation into the glass structure resulted in a net increase of 0.3406 g/cm3, whereas Cerium (Ce) addition resulted in a net in- crease of 0.2047 g/cm3. The Ho-doped S2 sample was found to have the greatest LAC value, despite the fact that seven glass samples exhibited identical behavior. The Ho-doped S2 sample had the lowest HVL values among the glass groups evaluated in this work, computed in the energy range of 0.015–15 MeV. The lowest EBF and EABF values were reported for Ho reinforced S2 sample with the highes LAC and density values. For all glass samples, a decrease in TF values was observed depending on the increase in thickness. Among the investigated glasses, Ho and Er reinforced samples (i.e., S2 and S4) showed the minimum TF values at used radioisotope energies. It can be concluded that Ho and Er type rare earth elements may provide the most effective gamma ray absorption properties when they are incorporated into the GeO2-B2O3-P2O5-ZnO- Tb2O3 system

We present the preparation phase and comprehensive analysis of nuclear radiation shielding characteristics of novel melt-quenched 20P2O5·30TeO2.(50-x)ZnO.xCdO (x = 0, 15, 20, 30, and 40 mol percent) quaternary-tellurite glasses. The primary objective is to compare the changes in nuclear radiation absorption qualities that come from maintaining high transparency and increasing the CdO contribution rate to maximum values, such as 40 mol%. Consequently, experimental gamma-ray and neutron transmission systems are used to investigate the monotonic impacts of increasing CdO reinforcement on the functioning of synthesized glasses utilizing the well-known melt-quenching method. For the determination of attenuation coefficients, a standard gamma-ray setup is used with an Ultra germanium detector and 133Ba radioisotope. In addition, using the Canberra NP-100B BF3 gas proportional detector, glass shields are bombarded with a 241Am/Be neutron source (10 mCi/4.5 MeV) using a gas proportional detector. The addition of 40% mole CdO to the basic composition of glass significantly improved the transition resistance to gamma and neutron radiation. Furthermore, it was shown that the degree of transparency in the C40 sample synthesized with a 40% CdO additive ratio was equivalent to that of an ideal transparent glass sample. Moreover, C40 sample had better gamma-ray attenuation properties than all other shielding materials (except for RS-520). According to the findings, C glasses have a greater capacity for neutron attenuation than investigated conventional moderators. It can be concluded that C glass family is an effective gamma-shield and neutron moderator for research and medical radiation applications. © 2022 Elsevier B.V. 2-s2.0-85131125980

Objective: Radioisotopes are used extensively in nuclear medicine. Analysis of occupational doses received by medical radiation workers, especially nuclear medicine staff dealing with radioisotopes, contributes significantly to enhancing safe practice and promoting radiation protection measures in the radiology department. The current study aimed to determine the time trend and the differences in occupational radiation dose among nuclear medicine workers. Methods: Readings of 394 OSL dosimeters were obtained from 31 medical workers and grouped into five worker groups (technologist, physician, nurse, radio-pharmacist, and radio-physicist). Results: The average number of workers dropped to 4.5 in 2020 and 2021 compared to 14.4 in 2014 to 2019. The average annual effective dose and skin dose for all workers based on measurements for a typical yearly workload of 5000 patients were 1.21 (±1.15) mSv and 2.86 (±1.32) mSv, respectively. The highest average annual effective and skin dose was 5.41 and 5.82 mSv, respectively. The NM technologist working in PET/CT received higher mean and maximum effective and skin doses than the other worker groups. Conclusion: The annual effective and skin doses were below the national legislation and international standards. However, improvements in radiation protection practices could be implemented to reduce occupational radiation dose to NM technologists, the most exposed worker group in this study. © 2022 The Author(s)

In this study, we extensively analyzed the structural, physical and gamma-ray attenuation properties of α-TeO2 CMS, which has unexpectedly been observed as a part of Sm2O3 doped TeO2–B2O3–V2O5 glasses synthesis process. The shape of α-TeO2 CMS was obtained from SEM analyses. Moreover, EDX, XRD and Raman examinations were utilized for systematic characterization of α-TeO2 CMS. In addition to experimental physical and structural studies on α-TeO2 CMSs, gamma-ray attenuation properties were also determined and compared with Quartz and some novel glasses such as PNCKM5, C25, SCNZ7 along with some commercial glasses such as RS253, RS253G18, RS323G19, RS360, RS520 using FLUKA general-purpose Monte Carlo code. EDX results indicated that only Te and O elements were available in the α-TeO2 CMS. The finding showed that gamma-ray attenuation competencies of α-TeO2 CMS is higher than many novel and commercial glasses in addition to traditional concrete shields. It can be concluded that further comparison studies can be done between normal glass structure and α-TeO2 CMS (or similar) occurred glass structures in terms of better understanding the total gamma-ray attenuation and the effect of α-TeO2 CMS. © 2021 The Author(s). The authors thank Taif University Researchers Supporting Project number (TURSP-2020/12), Taif University, Taif, Saudi Arabia. The APC was covered by "Dunarea de Jos" University of Galati, Romania.

The nuclear spectroscopy method has long been used for advanced studies on nuclear physics. In order to decrease costs and increase the efficiency of nuclear radiation investigations, quick and efficient solutions are required. The purpose of this research was to calculate the whole energy peak efficiency values for a range of gamma-ray energies, from 30.973 keV to 1408 keV, at various source-detector distances using the MCNPX Monte Carlo code, which is extensively used in nuclear medicine, industry, and scientific research. As a result, the modeled detectors' full-energy peak efficiencies were calculated and compared to both experimental data and Monte Carlo simulations. Experiment results and prior studies using Monte Carlo simulations were found to be very consistent with these results. The counting efficiency against source-detector distance is then calculated using the modeled detectors. The data we have show that LaBr3(Ce) has outstanding detection properties. This study's findings might be used to improve the design of detectors for use in wide range of high-tech gamma spectroscopy and nuclear research applications. WOS:000869715200006 Q2

In this study, Fe2O3, TiO2, and CdO semiconductor metal oxides were separately incorporated into the ZnO-MWCNT composite at different weight percentages. Accordingly, several experimental analyses on electrical, optical, and radiation shielding characteristics of coupled semiconductor metal oxides nanocomposites were performed to determine their monotonic impact on the investigated material properties. Moreover, gamma-ray shielding properties of these novel materials were determined using MCNPX general-purpose Monte Carlo code. At 5% oxide addition, the maximum electrical conductivity was found in all groups for all temperatures. Moreover, 5% oxide reinforcement resulted in the maximum reflection characteristics in all groups. Among the CdO doped materials, the CZnOCd5 sample exhibits the highest electrical conductivity behaviour at room and high temperatures. The Eg value calculated for the CZnOCd5 sample was 3.284 eV. The CZnOCd2.5 and CZnOCd5 samples had the greatest Eg values when compared to the pure sample and the samples from other groups. The CZnOCd5 sample has the highest reflectance value in the CZnOCd group's reflectance graph. On the other hand, the maximum gamma-ray attenuation properties were reported for CZnOCd5 sample. Among the analysed samples, the CZnOCd5 sample's characteristics provide a preliminary motivation for a more comprehensive analysis of this material and assessment of potential radiation protection applications., Princess Nourah bint Abdulrahman University, Riyadh, Saudi Arabia [PNURSP2022R149], Authors express their sincere gratitude to Princess Nourah bint Abdulrahman University Researchers Supporting Project Number (PNURSP2022R149) , Princess Nourah bint Abdulrahman University, Riyadh, Saudi Arabia.

In this paper the impact of adding the trivalent samarium (Sm3+) rare earth (RE3+) ions on the nuclear shielding performances of borate/sodium/potassium glasses with chemical form B2O3(70–x)/Na2O15/K2O15/Sm2O3; x = 0.0–2.0 mol% was examined. Material densities were enhanced quantitatively from 2.22 to 2.48 g/cm3. Several radiation shielding parameters have been determined in the 0.15–15 MeV photon energy range via MCNPX simulation code and Phy-X/PSD software. Results showed that the addition of Sm3+ ions to the glasses improved the linear (LAC) and mass (MAC) attenuation coefficients. The Sm2.0 sample (rich with Sm3+ ions and with a high density) has the highest LAC and MAC at all photon energy values under investigation. The half-value layer (T1/2) values of the studied Sm-glasses followed the trend: (T1/2)Sm0.0> (T1/2)Sm0.1> (T1/2)Sm0.3> (T1/2)Sm0.5> (T1/2)Sm0.7> (T1/2)Sm1.0> (T1/2)Sm1.5> (T1/2)Sm2.0. The mean free path (λ) has a similar trend as T1/2. The numerical results of effective atomic number (Zeff) were: Sm0.0 = 10.538, Sm0.1 = 10.70646, Sm0.3 = 11.03259, Sm0.5 = 11.28569, Sm0.7 = 11.53882, Sm1.0 = 11.91848, Sm1.5 = 12.42718, Sm2.0 = 12.9175 at 0.015 MeV, and Sm0.0 = 8.36553, Sm0.1 = 8.42831, Sm0.3 = 8.55388, Sm0.5 = 8.67944, Sm0.7 = 8.80502, Sm1.0 = 8.99335, Sm1.5 = 9.28877, Sm2.0 = 9.58377 at 15 MeV. The Sm2.0 glass sample has the greatest Zeff value across all gamma-ray energies. This condition is likewise associated with the highest Sm (Z = 62) content in Sm2.0 when compared to the other studied glasses. In addition, the Sm2.0 sample had the lowest exposure (EBF) and energy absorption (EABF) build-up factors values among the glass samples under investigation. All the obtained observations confirm that the Sm-glass samples can be considered promising materials for attenuation of nuclear radiations. © 2022 The Author(s) Taif University, TU: TURSP-2020/12 The authors thank Taif University Researchers Supporting Project number (TURSP-2020/12), Taif University, Taif, Saudi Arabia.

For 662, 1173, 1275, and 1333 keV gamma-ray energy, photon transmissions, linear attenuation coefficients, half value layer, tenth value layer, and mean free path values of bismuth-borophosphate glasses were measured experimentally. Then, the measured findings were compared to the FLUKA code. The FLUKA code findings agreed well with the experimental results. Furthermore, the findings show that adding Bi2O3 to the glass network improves the shielding properties. The current data reveal that when the Bi2O3 content rises, so does the absorbance. Furthermore, the optical constants of the present gasses, such as optical band gap, phonon energy, and tails of localized states, were examined. Fourier transform infrared (FTIR) spectrometer was used to analyze the Fourier transform infrared (FTIR) spectra of our samples at room temperature in the 4000–400 cm−1 wavenumber range. From a shielding standpoint, bismuth-borophosphate glasses offer excellent gamma-ray shielding properties. © 2022

The oxide of the rare earth element gadolinium has the chemical formula Gd2O3. Also known as gadolinium sesquioxide, gadolinium trioxide, and Gadolinia, gadolinium oxide. In this study, various types of fundamental cross-sections, attenuation coefficients, build-up factors and individual transmission factors of high density gadolinium-tungsten-boron trioxide glasses with a chemical composition of (70-x)WO3-xGd2O3 –30B2O3 (where x: 17.5, 20.0, 22.5, 25.0 and 27.5 mol%) are determined using advanced Monte Carlo methods. In addition, gamma transmission factors (TFs) for a range of medical and industrial radioisotopes were calculated using MCNPX (version 2.7.0) Monte Carlo code. The investigated glasses were classified Gd17.5, Gd20.0, Gd22.5, Gd25.0, and Gd27.5 in accordance with xGd2O3. Our findings suggest that the Gd27.5 sample (with highest of Gd2O3 content mol. %) has possessed the maximum linear (µ) and mass (µ/ρ) attenuation coefficients at all gamma-ray energies investigated. The coded glass sample Gd27.5 is achieved the maximum effective atomic number (Zeff) and effective electron density (Neff) owing its superior attenuation properties. In terms of build-up factors, increasing the concentration of xGd2O3 in glasses is decreased the EBF and EABF values for all mean free path values (0.5–40 mfp). At a thickness of 3 cm, the lowest transmission factor (i.e., highest attenuation) was verified for all Gd17.5-Gd27.5 glasses investigated. Consequently, the Gd27.5 sample exhibits superior radiation shielding properties for a large range of photon energy and various medical and industrial radioisotope energies. © 2022 Elsevier GmbH Q2

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. © 2022 The Author(s) 2-s2.0-85129475632

We report the physical, optical and nuclear radiation attenuation behaviours of tellurite–germanate (TeO2–GeO2–PbO) glasses reinforced with varying amounts of Eu2O3. The samples were synthesised using the conventional melt-quenching method and had the following composition (in wt.%): 33.34TeO2 - 33.33GeO2 - 33.33PbO (TGP). Different concentrations of Eu2O3 (in wt.%) were added to the glass composition, labelled TGP1, TGP2 and TGP3. The physical, optical and nuclear radiation attenuation properties were measured using both experimental and theoretical methods. At room temperature, the visible to near-infrared optical absorption spectrum ranged from 400 to 900 nm. The TGP1 sample with 1 wt% The Eu2O3 additive exhibited the lowest absorbance and the highest transparency. The TGP1 sample also exhibited the highest nuclear radiation absorption properties. The gamma-ray absorption capabilities of TGP1 were demonstrably superior to those of various types of glass shields and other old- and new-generation concrete-shielding materials. Thus, adding 1 wt% Eu2O3 to tellurite–germanate glasses would ‘improve nuclear radiation absorption and optical properties. It can also be concluded that expanded scientific community investigations in this area would be a significant step toward gaining a deeper understanding of these glass structures and determining what other optimisation tasks the addition of 1 wt% Eu2O3 can accomplish.

We report the optical, physical, structural, and heavy charged particle absorption parameters of CdO doped P2O5-TeO2-ZnO ternary glass structures with a nominal composition of 20 P2O5.30TeO2.(50-x)ZnO.xCdO (x = 0, 2, 4, 6, 8, 10 mol. %). Physical as well as optical characteristics of the synthesized glasses are measured using experimental methods. ZnO/CdO translocation is caused an increase in the density of the synthesized samples. Synthesized glasses are reported along with seventeen different bands as a result of deconvolution processes. The structure is formed more tightly and regularly with ZnO/CdO translocation process. As a result of the evaluation of the absorption edge, transmittance of the glass without CdO additive is reported around 338 nm in the 20–30 % transmittance region, the absorption edge of all the glasses doped with CdO is shifted to around 336 nm. According to results, un-doped C0 glass is observed more unstable and far from homogeneous than doped glasses with the largest Urbach energy value (0.1506 eV), while C10 glass is observed as much more stable and uniform when compared to all glasses in this study with a value of 0.1311 eV. Moreover, projected range values of alpha and protons grew as the energy level increased. The shortest lengths that alpha and protons may travel at the same energy levels are reported for the C10 sample, which has the highest CdO contribution as well as the highest glass density. C10 glass sample is reported to have the maximum degree of clarity, making it one of the most important qualifying requirements for shields in medical radiation facilities, where the observation of both the patient and the physical radiation source is crucial. It can be concluded that the investigated ZnO/CdO translocation process may be seen as a beneficial tool for P2O5-TeO2-ZnO ternary glass structures in terms of enhancing optical, physical, and heavy charged particle attenuation properties. Q2

Gamma-ray shielding properties of high dense glassy system (bismuth fluoro-lead-borate doped with chromium (III) ions) with composition of (25-x)PbF2–25Bi2O3–49.8B2O3–0.2Cr2O3- xCaF2- (where x = 0 (S1), 5 (S2), 10 (S3), 15 (S4), 20 (S5), and 25 (S6) mol%) have been investigated. Phy-X/PSD software was used to achieve this purpose in photon energy range (0.15–15 MeV). Additionally, the superior glass shield sample was compared to several types of glass and concrete shields. Results revealed that each photon energy value investigated the maximum linear attenuation coefficient (µm) values for the S1 glass sample with the heaviest element contribution in its structure were detected at the maximum level. In terms of the µm, there was a difference of roughly 0.5 cm2/g in the S1 and S6 glasses. The S1 sample with the highest µm also had the lowest T0.5 and mean free path (λ). The heavy element contribution to the S1 sample was reflected in the effective atomic number values, which provided the S1 sample with the highest Zeff values. Values of exposure and energy absorption buildup factors (EBF and EABF) were confirmed that the sample S1 has the minimum values. Our findings showed that S1 sample may be considered as superior gamma-ray shielding properties among all studied glasses. © 2022 Elsevier GmbH 2-s2.0-85136518668 WOS:000863097900002 Q2

5CaF2–5BaF2 – 60B2O3–10TeO2 – (20-x)Na2O – xDy2O3: (0.5 ≤ x ≤ 2.5 mol percent) glasses were studied for their physical, mechanical, and gamma radiation resistance. The density of Dy0.5 and Dy2.5 glass samples containing 0.5 and 2.5 mol of Dy2O3 was changed from 2.98 to 3.09 g/cm3, respectively. The estimated values of longitudinal (LB-C) were altered from 171.085 to 165.390 GPa, bulk (KB–C) from 105.100 to 102.680 GPa, Young's (EB-C) from 128.602 to 122.674 GPa, and shear (SB–C) from 49.612 to 47.150 GPa for mechanical characteristics (GPa). The Poisson's ratio (σB-C) was varied between 0.296 and 0.300. The MCNPX code and Py-MLBUF online calculation platform were used to calculate mass attenuation coefficients for all Dyx-glasses. In terms of quantitative values, the acquired results are in good agreement. For all photon energies, the Dy2.5 glass sample exhibits the highest linear (μ) and mass (μm) attenuation coefficients. All analyzed Dyx-glasses exhibit a similar trend in half-value layer (T1/2) and mean free path (MFP), (T1/2, λ)Dy0.5 > (T1/2, λ)Dy1.0 > (T1/2, λ)Dy1.5 > (T1/2, λ)Dy2.0 > (T1/2, λ)Dy2.5. Over the whole gamma-ray energy range, the Dy2.5 sample has the highest effective atomic number (Zeff) values. Across the whole photon energy and penetration depth range, the Dy2.5 has the lowest EBF and EABF values. Because of the maximum contribution of Dysprosium (III)-oxide, the Dy2.5 sample can be deemed superior in terms of gamma-ray shielding qualities. © 2022 The Author(s) Taif University, TU: TURSP-2020/12 The authors thank Taif University Researchers Supporting Project number (TURSP-2020/12), Taif University, Taif, Saudi Arabia.

Using advanced Monte Carlo simulation techniques and theoretical methodologies, a thorough investigation on the gamma-ray shielding properties of several heavy metal oxide glasses were performed. The general-purpose Monte Carlo code MCNPX (version 2.7.0) was used to simulate gamma-ray transmission to determine fundamental attenuation coefficients. The acquired findings were compared to Phy-X/PSD to confirm that the outputs were consistent. Additionally, other gamma-ray shielding parameters were computed and studied throughout a broad photon energy range of 0.015 MeV–15 MeV. From A to F glass samples, a sharp density increase from 5.99 g/cm3 to 8.9 g/cm3 was found. As a result, the F sample was found to have the highest linear attenuation coefficients. Our results indicate that increasing the amount of Bi reinforcement improved the material's overall gamma-ray attenuation properties. The F sample with the highest Bi reinforcement in its glass structure was subsequently shown to have superior gamma-ray shielding characteristics. Finally, we compared the F sample's half-value layer values to those of other commercial glass shields, various concretes, and other glass shields investigated in the literature. As a consequence of the benchmarking procedure, it has been determined that the F sample has better shielding capabilities than other shielding materials. It can be concluded that heavy metal oxide glasses offer apparent benefits in terms of more efficiently attenuating incoming gamma-rays. Additionally, it can be concluded that applying high Bi to heavy metal oxide glasses is a beneficial strategy for improving the gamma-ray attenuation capabilities of heavy metal oxide glasses. © 2022 The Author(s) Princess Nourah Bint Abdulrahman University, PNU Authors express their sincere gratitude to Princess Nourah bint Abdulrahman University Researchers Supporting Project.

Introduction: Whole-body computed tomography (WBCT) is still debatable and a source of excessive radiation exposure when screening individuals with suspected blunt multiple trauma. Objective: This study aims to develop institutional Diagnostic Reference Level's (DRL) value and estimate effective organ doses for poly-trauma patients who underwent WBCT examination. Method: Retrospective analysis for patients undergone WBCT scans after being traumatized and admitted to the emergency room. Effective and organ dose estimated for 78 patients. Sequence parameters and CT indices were retrieved from the CT system. Data analysis was done using SPSS 20.0 (SPSS Inc, Chicago, IL, USA). Results: 84.3% of the patients were male, while 15.7% were female. 88% of the patients had a road traffic accident, and the rest fell from height. The effective dose was estimated as 34.5-35.3 mSv in males and females, respectively, while the organ doses ranged from 10.2 to 63.7 mGy. Conclusion: WBCT is a standard diagnostic radiological tool for urgent evaluation of patients with serious trauma. However, WBCT scanning comes with significant radiation exposure and the risk of developing cancer. Therefore, the WBCT should be clinically justified, and dosage reduction measures should be applied. WOS:000913211500006 Q3

In this study, four new phosphate-based glasses with the compositions of CaO–Na2O–K2O–P2O5 (PN system), CaO–Na2O–K2O–Al2O3–P2O5 (PA system) and CaO–Na2O–K2O–Al2O3–SiO2–P2O5 (PS system) were synthesized and characterized through experimental gamma-ray and neutron spectroscopy methods. Glass densities were then measured experimentally and evaluated theoretically. Next, a high purity Germanium (HPGe) detector was used for determining the fundamental gamma-ray transmission parameters in 35.4–383 keV gamma-ray energies emitted from 133Ba source (Radioactivity: 3Ci). Additionally, the experimental setup was used to determine the equivalent dose (EAD) to get a better knowledge of fast neutron attenuation. Our findings indicate that experimental gamma-ray transmission measurements are consistent with standard theoretical data (EpiXS). Consequently, PA10 was shown to have higher gamma-ray and neutron attenuation capabilities when compared to the other glass samples studied. Our outcomes showed that increasing the molar contribution of Al2O3 to the phosphate-based glasses increased not only their transparency but also their gamma-ray and neutron attenuation capacities. It can be concluded that substituting Al2O3 for P2O5 is a functional and monotonic tool for improving the optical, gamma-ray, and neutron attenuation of phosphate-based glasses, which are being evaluated as prospective shielding materials for medical and industrial radiation facilities. © 2022 Elsevier Ltd and Techna Group S.r.l. 2-s2.0-85123848047

This study aimed to investigate the protective properties of Bi2O3 heavy metal oxide-doped glassy portable containers and the effect of reinforcement amount on these properties using the MCNPX (version 2.6.0) general-purpose Monte Carlo code. Accordingly, 60Co and 137Cs radioisotopes were defined as point isotropic radioactive sources to be transported with the newly designed containers. Four containers with different heavy metal oxide additives varying between 5% and 20% were designed and the deposited energy (MeV/g) values in the air were calculated for both 60Co and 137Cs radioisotopes. According to the findings of the first phase of the investigation, the sample (S4) with a 20% Bi2O3 additive ratio showed the highest protective properties and the least amount of deposited energy amount in the air. In the second and benchmarking phase of the investigation, we compared the amount of deposited energy in the air for the superior S4 glass container and a concrete container with a high amount of bitumen additive. The findings demonstrated that the S4 portable glass container with a 20% Bi2O3 reinforcement provided significantly lower deposited energy in the air and therefore greater nuclear safety than the concrete container. Heavy metal oxide-doped glass may be considered a viable choice for nuclear waste management and transportation operations due to its nuclear safety properties and superior physical, optical, and mechanical capabilities in comparison with concrete. WOS:000864071400002 Q1 - Q2

Bismuth based fluorophosphate (PBNS) glasses doped with samarium ions were fabricated by well-known melt quenching method. The structural, optical and fluorescence properties of PBNS glasses, were extensively investigated via XRD, FTIR, EDAX, optical absorption and fluorescence emission along with lifetime decay analysis. The intensity parameters (Ω2, Ω4, Ω6) were calculated using the Judd – Ofelt hypothesis, which follows the Ω4 > Ω6 >Ω2 trend. PBNSSm glasses doped with 1.0 mol% samarium ions (PBNSSm10) had a greater emission peak intensity than the produced glasses according to the emission spectra. The 4G5/2 → 6H7/2 transition emitting the radiation at 597 nm was more intense than the other transitions and got higher values for optical gain bandwidth (10.70 x 10−25 cm3), stimulated emission cross-section (10.05 x 10−20 cm2) branching ratio (0.48), and optical gain parameter (28.65 x 10−25 cm2s). The emission spectral results have been used to evaluate the colorimetric analysis of the 1931 CIE coordinates, and CCT values fall in the visible spectrum region. Moreover, the degree of protection of the synthesized PBNS glasses against gamma radiation was also evaluated. The obtained results suggested that the PBNS glass doped with 1.0 Sm3+ ions could be useful for multi-band visible laser applications. It was also concluded that 2.0% Sm3+ addition effectively increases the gamma-ray shielding properties of PBNS glasses, and therefore PBNSSm20 can be an alternative shielding material. WOS:000861371700005 Q2

The purpose of this study is to conduct a thorough examination of the direct and indirect impacts of increasing the quantity of heavy WO3 on gamma-ray transmission, shielding and mechanical properties for some selected barium-phosphate-tungsten glasses. Accordingly, mechanical properties of barium-phosphate-tungsten oxides with chemical formula (50-x)P2O5-50BaO-xWO3 (x = 0.0(S1), 5.0(S2), 10(S3), and 15(S4)) mol% was evaluated using Makishima-Mackenzie model. Next, newly online Phy-X/PSD software and Monte Carlo code were used to examine the gamma radiation characteristics. Gamma-ray transmission factor (TF) values were calculated for S1, S2, S3 and, S4 glass samples for a range of well-known radioisotope energies such for 67Ga, 57Co-57, 111In-111, 133Ba, 201Tl, 99 mTc, 51Cr, 131I, 58Co, 137Cs, 60Co. The total packing density (Vt) was enhanced from 0.589 for S1 glass sample (free with WO3) to 0.605 for S4 glass sample (with highest WO3 =15 mol%). The total energy dissociation (Gt) of the investigated glasses was increased with increasing the WO3 content: from 51.7 (kJ/cm3) for S1 glasses to 52.45 (kJ/cm3) for S4 glasses. All mechanical moduli were improved with increasing the tungsten trioxide concentration in the studied glasses. Poisson's ratios were increased with increasing the WO3 concentration. The trend of linear (LAC) and mass attenuation (MAC) coefficients were followed as: (LAC, MAC) S1 < (LAC, MAC) S2 < (LAC, MAC) S3 < (LAC, MAC) S4. Half (HVL) and tenth (TVL) value layers have the trend as (HVL, TVL) S1 > (HVL, TVL) S2 > (HVL, TVL) S3 > (HVL, TVL) S4. The effective atomic number (Zeff) and electron density (Neff) have the same trend. The lowest transmission Factor (TF) values for all glass specimens were examined at a thickness of 3 cm. Furthermore, the S4 sample displayed the least transmission tendency across all glass thicknesses evaluated. © 2022 The Authors Princess Nourah bint Abdul Rahman University Researchers Supporting Project Number (PNURSP2022R149).

A comprehensive set of experimental measurements was carried out to investigate the influence of Nd3+ ions on the structure, electrical conductivity, and gamma-ray protection of CdO/PbO-B2O3 glasses containing neodymium oxide with the chemical formula 20CdO/20PbO/(60-x)B2O3/xNd2O3 (0 ≤ x ≤ 4 wt%) (5.034-5.232 g/cm3). Raman spectra have been obtained over a range of 1600-180 cm−1, and electrical conductivity (σ) has been measured at frequencies of 0.120, 1, 10, and 100 KHz, as well as at other frequencies. In this study, gamma-ray attenuation has been studied at various gamma-ray energies (ranging from 0.081 to 2.614 MeV). The results revealed that the PbO in the investigated glass networks fills the interspaces of [BO3] units with Pb2+ ions, therefore serving as a network member. In general, it was found that (σ) of the examined glasses falls as temperature increases, reaching its lowest value at the composition's transition temperature. Above this transition temperature, conductivity rises. Using 0.662 MeV, the studied samples exhibited experimental linear attenuation coefficients (μexp.) of 0.3369 cm−1, 0.3401 cm−1, 0.3434 cm−1, 0.3467 cm−1, and 0.3501 cm−1 (for the Nd-0.0, Nd-1.0, Nd-0.2, Nd-0.3, and Nd-4.0 glasses, respectively). With respect to the half value thickness (T1/2) and mean free path (λ), the Nd-4.0 sample has the lowest values at all of the gamma-ray energies tested. According to these results, the Nd-4.0 glass sample exhibits higher attenuation capabilities against ionizing radiation when compared to the other samples. © 2022

High-Entropy Alloys (HEAs) are regarded as potential structural materials for fusion and next-generation fission reactors, which will be required to fulfil growing nuclear energy demands. In this study, a HEA-composite was synthesized by adding B4C to an HEA containing Ni. The microstructure of the obtained HEA-composite was examined and the changes in its mechanical properties were revealed. Additionally, the nuclear radiation shielding properties of the Ni-containing HEA, and the HEA-composite are investigated using experimental and theoretical methods. Our initial findings showed that with the addition of 2.5% B4C to the alloy, the hardness increased more than two times. The addition of B4C to the HEA matrix resulted in a more than 90% and a nearly twofold increase in compressive strength. The shielding qualities of gamma-ray and neutron radiation were investigated using experimental and theoretical approaches. Our findings demonstrated that increasing the B4C reinforcement considerably enhanced the composite material's neutron attenuation capabilities. On the other hand, no significant change in the gamma-ray shielding characteristics of HEA and HEA-composite samples was observed. The gamma-ray shielding characteristics of HEA and HEA-composite samples were compared to those of other alloy shields and commercial products. Our findings indicate that both HEA and HEA-composite samples exhibit superior gamma-ray shielding characteristics when compared to the control samples. It can be concluded that increasing B4C reinforcement may be a multifunctional tool in terms of improving the mechanical properties as well as neutron attenuation properties for advanced applications in nuclear radiation facilities and next-generation fission reactors. Additionally, due to their promising material features and higher gamma-ray shielding capabilities compared to other kinds of alloys and commercial shields, HEAs may be beneficial materials. © 2022 Elsevier Ltd 2-s2.0-85130328135

We report the synergistic effects of boron nitride and graphene nanosheets on physical, structural, and nuclear radiation attenuation properties of polyester matrix-incorporated nanocomposites. Some critical material properties are thoroughly evaluated for several types of synthesized samples. Polyester is employed to strengthen graphene and boron nitride nanolayers, and their characteristics are investigated in detail. Additionally, we report the gamma-ray and fast neutron attenuation characteristics of synthesized nanocomposites to get a better understanding of the reinforcing effect as a function of material type and weight percentage. Thermal analysis findings indicate that adding graphene lowers the decomposition temperature but co-adding graphene and BNNS enhances thermal decomposition in comparison to graphene itself. Tensile tests showed that the inclusion of both GRP and GRP/BNNS strengthens the material. Among the polyester composite samples analyzed, the G3 sample with the most GNP reinforcement had the lowest HVL values throughout the broadest range of energy levels investigated. The recent findings may be beneficial to the scientific community in terms of incorporating these reinforcing types and ratios into polyester materials for a variety of applications, including industrial and research purposes. © 2022 2-s2.0-85130401014

The Pakkanadu Ultramafic–Alkaline–Carbonatite complex of Salem district has been studied using geochemical and remote sensing aspects. The samples collected from different locations of Pakkanadu were taken for mineralogical and geochemical analysis (XRF). Visible Near Infrared (VNIR) and Short Wave Infrared (SWIR) region of Advanced Spaceborne Thermal Emission and Reflection Radiometer (ASTER) data were used to retrieve the different band combinations to demarcate the carbonatite rock from adjacent lithologies. The image processing analysis of True Color Composite (1, 2, 3), False Color Composite (3, 2, 1), PCA derived band combinations of (3, 4, 8), and band ratio (2/1, 5/4, 8/2) outputs have given enhanced images which helped to demarcate the boundaries of litho units. Moreover, gamma-ray shielding competencies of studied complex materials were determined in the 0.015–15 MeV photon energy range. Our finding showed that the dunite sample, which has the maximum Fe2O3 amount in composition, has superior shielding properties among the investigated materials. It can be concluded that nominal compositions and material densities of studied natural materials have a direct impact on investigated properties. It can also be concluded that dunite's superior shielding properties are worth investigating for other types of radiations such as neutron and heavy ions. © 2022 The Author(s) 2-s2.0-85123939520