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    Analysis of the Radiological, Mineralogical and Long-Term Sustainability of Several Commercial Aswan Granites Used as Building Materials
    (MDPI, 2022) Zakaly, Hesham M.H.; Awad, Hamdy A.; Moghazy, Nasser M.; Tekin, Hüseyin Ozan; Rabie, Abdalla; Fawzy, Mona M.; El-Tohamy, Amira M.; Ene, Antoaneta; Issa, Shams A.M.
    The widespread usage of granite in the building sector motivated us to conduct this research and examine the material’s sustainability in terms of the investigated characteristics. The purpose of this paper is to discuss the statistical analysis results for the mineralogical impact on radiological hazards indices, such as the equivalent of radium, absorbed gamma dose rate, annual effective dose, internal and external hazard indices, as well as the gamma-ray index, that were cal-culated to estimate the environmental risks associated with these granites used as building materi-als, to protect the public from excessive radioactivity exposure. We focused primarily on statistical significance at a 95% confidence level. We employed a non-parametric test (Kruskal–Wallis Test) rather than a one-way ANOVA, to determine the statistical significance of the samples due to the lack of homogeneity or normality among them. To assess the difference between the samples, we used the Mann–Whitney Test on each pair of samples. Additionally, Pearson correlation coefficients for all the mineralogical results are computed. The presence of K-rich minerals (Kefeldspars, biotite) and accessories such as uranophane, uranothorite, allanite, xenotime, fergusonite, aeschynite, zir-con, cassiterite, apatite, and sphene, which are mostly found in granitic rocks, determines the level of natural radioactivity of the investigated granites. Most of the rock samples analyzed have indicators of radioactive dangers that are within the acceptable level range, indicating that they are suitable for use as building materials. On the other hand, some samples have environmental criteria that are higher than international standards, indicating that they are unsuitable for use as construction materials. © 2022 by the authors. Licensee MDPI, Basel, Switzerland.
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    Assessment of the usability conditions of Sb2O3-PbO-B2O3 glasses for shielding purposes in some medical radioisotope and a wide gamma-ray energy spectrum
    (DE GRUYTER POLAND SP Z O O, 2022) Almisned, Ghada; Şen Baykal, Duygu; Kılıç, Gökhan; Susoy, Gülfem; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan
    We report some fundamental gamma-ray shielding properties and individual transmission factors (TFs) of five distinct glass samples with a nominal composition of xSb(2)O(3)center dot (40 - x)PbO center dot 60B(2)O(3)center dot 0.5CuO and (where; 0 <= x <= 40 mol%). Phy-X/PSD and MCNPX (version 2.7.0) Monte Carlo code are utilized to determine several critical parameters, such as cross-sections, attenuation coefficients, half and tenth value layers, build-up factors, and TFs. A general transmission setup is designed using basic requirements. Accordingly, TFs are evaluated for several medical radioisotopes. Next, the gamma-ray shielding parameters and TFs are assessed together in terms of providing the validity of the findings. Our results showed that there is a positive contribution of increasing Sb2O3 amount in the glass matrix owing its direct effect to the density increment as well. This positive effect on gamma-ray shielding properties is also observed for decreasing mean free path values from S1 to S5 samples. The exposure build-up factor (EBF) and energy absorption build-up factor (EABF) values, increasing the quantity of Sb2O3 supplementation, resulted in a general reduction in EBF and EABF values (i.e., from 0.5 to 40 mfp). When the quantity of Sb2O3 rises from S1 to S5, the collision rate of incoming gamma rays in glass samples increases significantly. The TF figures reveal that S5 showed the least transmission behavior across all the above-mentioned studied glass thicknesses. It can be concluded that increasing the Sb2O3 additive is a beneficial and monotonic technique, when the gamma-ray shielding qualities or TF values must be further enhanced.
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    Bacterial MgSe complex nanoparticle synthesis and electrical characterization of fabricated Ag/MgSe/p-Si hetero-structure under dark and illumination
    (Cell Press, 2023) Cakici, T.; Ozdal, O. Gur; Almousa, N.; Yildiz, F.; Khalil, H.; Ene, Antoaneta; Zakaly, Hesham M. H.
    The Pseudomonas aeruginosa OG1 strain was used in the bacterial synthesis of MgSe compound nanoparticles. The obtained samples were subsequently shaped into nanocrystalline MgSe films, and their optical, structural, morphological, and electrical properties were assessed on glass and p-Si substrates. Structural and morphological characterizations showed that the fabricated thin film samples have a polycrystalline structure with high quality and uniform grain sizes. The MgSe films produced on glass substrates exhibit a direct spectral band gap of 2.53 eV, according to optical measurements. The Ag/MgSe/p-Si layered diode structure was fabricated using the produced MgSe nanoparticles and then characterized by electrical properties. Electrical measurements were carried out under these two conditions to assess the effects of dark and illumination conditions on the band dynamics of the heterostructure devices. Under illumination, the barrier height decreased while the interface density states distribution increased. These measurements showed that using bacterial-assisted grown MgSe nanocrystalline films, the developed Ag/MgSe/ p-Si device structure exhibited a remarkable photoresponse and stable rectifying property. Green synthesis methods for the production of these nanocrystalline materials have the potential to offer low-cost alternatives for photosensitive applications.
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    Binary contributions of Dy3+ ions on the mechanical and radiation resistance properties of oxyfluoroborotellurite Dyx-glasses
    (Elsevier Editora Ltda, 2022) Rammah, Y.S.; Issa, Shams A.M.; Tekin, Hüseyin Ozan; Badawi, Ali; Ene, Antoaneta; Zakaly, Hesham M.H.
    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 (?B-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 (?) and mass (?m) attenuation coefficients. All analyzed Dyx-glasses exhibit a similar trend in half-value layer (T1/2) and mean free path (MFP), (T1/2, ?)Dy0.5 > (T1/2, ?)Dy1.0 > (T1/2, ?)Dy1.5 > (T1/2, ?)Dy2.0 > (T1/2, ?)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)
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    Calculation of NaI(Tl) detector efficiency using Ra-226, Th-232, and K-40 radioisotopes: Three-phase Monte Carlo simulation study
    (DE GRUYTER POLAND SP Z O O, 2022) Tekin, Hüseyin Ozan; Almisned, Ghada; Issa, Shams A. M.; Zakaly, Hesham M. H.; Kılıç, Gökhan; Ene, Antoaneta
    Thallium-activated sodium iodide (NaI(Tl)) detectors can be used in gamma cameras, environmental radiation assessments, including radiation emission levels from nuclear reactors, and radiation analysis equipment. This three-phase investigation aimed to model a standard NaI(Tl) detector using the Monte Carlo N-Particle eXtended (MCNPX) general-purpose Monte Carlo simulation techniques. Accordingly, a standard NaI(Tl) detector was designed along with the required properties. Next a validation study of the modelled NaI(Tl) detector has been performed based on the experimental results for absolute detector efficiency values obtained from Ra-226, Th-232, and K-40 radioisotopes. Our findings indicate that the obtained absolute detector efficiency values are quite close to used experimental values. Finally, we used the modelled detector for determination of mass attenuation coefficients of Ordinary concrete, Lead, Hematite-serpentine concrete, and Steel-scrap concrete at 186.1, 295.22, 351.93, 609.31, 1120.29, 1764.49, 238.63, 911.2, 2614, and 1460.83 keV gamma-ray energies. Additionally, according to our findings, mass attenuation coefficients obtained from the newly designed detector are compatible with the standard NIST (XCOM) data. To conclude, continuous optimisation procedures are strongly suggested for sophisticated Monte Carlo simulations in order to maintain a high degree of simulation reliability. As a result, it can be concluded that the validation of the simulation model is necessary using measured data. Finally, it can also be concluded that the validated detector models are effective instruments for obtaining basic gamma-ray shielding parameters such as mass attenuation coefficients.
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    Clinical comprehensive and experimental assessment of the radioprotective effect of Annona muricata leaf extract to prevent cellular damage in the ileum tissue
    (De Gruyter Open Ltd, 2022) Elmas, Özlem; Şahin, Havva Hande Keser; Keskin, Emrah; Güven, Berrak; Uslu Erdemir, Rabiye; Almisned, Ghada; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan
    We report the radioprotective attitude of Annona muricata (AM) leaf extract as antioxidant material to prevent cellular damage in the ileum tissue. The protective effects of an ethyl acetate extract of AM leaves are comprehensively investigated against radiation-induced ileal damage in numerous rats. Thirty-two adult female rats were separated into 4 groups (3 intervention groups and 1 control) as follows: controls received 0.01 mL/kg distilled water, the AM group received 300 mg/kg AM leaf extract, the ionizing radiation (IR) group received a single dose of whole body radiation (8.3 Gy) after 0.01 mL/kg saline treatment, and the AM + IR group received 300 mg/kg AM leaf extract treatment and were subjected to whole body radiation (8.3 Gy) 1 h after the last gavage. All treatments are administered by oral gavage once a day for 9 days. At the end of the experiment, biochemical total oxidant status (TOS, interleukin-6, and caspase) and histological examinations are performed on blood samples as well as ileum tissue. TOS levels are found to be significantly high in rats, which received irradiation, and those in the AM group when compared to controls. These findings suggest that AM has radioprotective effects on ileum tissue, likely because of its antioxidative properties. The findings of this research may contribute to the minimizing of major side effects induced by excessive radiation exposure in patients undergoing radiotherapy and may serve as a significant impetus for further assessments. However, future studies are highly recommended to confirm safety and to determine extraction technique and dosage before human use can be considered.
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    A closer look at the efficiency calibration of LaBr3(Ce) and NaI(Tl) scintillation detectors using MCNPX for various types of nuclear investigations
    (Elsevier Ltd, 2022) Almisned, Ghada; Zakaly, Hesham M.H.; Ali, Fatema T.; Issa, Shams A.M.; Ene, Antoaneta; Kılıç, Gökhan; Ivanov, V.; Tekin, Hüseyin Ozan
    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.
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    A comprehensive evaluation of the attenuation characteristics of some sliding bearing alloys under 0.015–15 meV gamma-ray exposure
    (MDPI, 2022) Algethami, Merfat; Ibraheem, Awad A.; Issa, Shams A. M.; Tekin, Hüseyin Ozan; Ene, Antoaneta; Pyshkina, Maria; Rashad, Mohamed; Almisned, Ghada; Zakaly, Hesham M. H.
    In this study, three different sliding bearing alloy samples were investigated in terms of their performance on attenuation characteristics and behavioral attitudes under 0.015–15 MeV gamma-ray exposure. Accordingly, different types of advanced calculation methods were utilized to calculate the radiation shielding parameters. Next, several gamma-ray shielding parameters and exposure rates in addition to fast neutron removal cross-section were determined. Furthermore, exposure and energy absorption buildup factors were determined by using G-P fitting method. Mass attenuation coefficients (MAC) values were recorded as 2.5246, 2.5703, and 2.5827 (cm2 /g) for Alloy1, Alloy2, and Alloy3 samples at 15 MeV photon energy, respectively. At 40 mfp, the highest EBF values were reported as 1,376,274, 1,003,593, and 969,373 for Alloy1, Alloy2, and Alloy3 samples. The results of this extended investigation showed that the Alloy3 sample with the highest Pb reinforcement amount has superior shielding capability among the investigated samples. It can be concluded from the results that substitution of Pb with Bi in the recent alloy structure has a monotonic effect on different types of shielding parameters. Therefore, it can also be concluded that Pb is a remarkable tool for the improvement of the shielding properties of studied alloy structures. © 2022 by the authors. Licensee MDPI, Basel, Switzerland.
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    Comprehensive evaluation on gamma radiation resistance of chromium (III) ions incorporated bismuth fluoro-lead-borate glasses
    (Elsevier, 2022) Issa, Shams A.M; Almisned, Ghada; Tekin, Hüseyin Ozan; Zakaly, Hesham M.H.; Ene, Antoaneta; Ibraheemh, Awad A.; Rammah Y.S.
    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 (?). 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
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    A critical evaluation on nuclear safety properties of novel cadmium oxide-rich glass containers for transportation and waste management: benchmarking with a reinforced concrete container
    (FRONTIERS MEDIA SA, 2022) Almisned, Ghada; Şen Baykal, Duygu; Kılıç, Gökhan; İlik, Erkan; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan
    We examine the nuclear safety properties of a newly designed cadmiumoxide-rich glass container for nuclear material to a bitumen-reinforced concrete container. Individual transmission factors, detectormodelling, and energy deposition (MeV/g) in the air are calculated using MCNPX (version 2.7.0) general purpose Monte Carlo code. Two container configurations are designed with the material properties of cadmium dioxide-rich glass and Concrete + Bitument in consideration. First, individual transmission factors for 60Co and 137Cs radioisotopes are calculated. To evaluate potential environmental consequences, energy deposition amounts in the air for 60Co and 137Cs are also determined. The minimum gamma-ray transmission rates for two container types are reported for a cadmium dioxiderich glass container. In addition, the quantity of energy deposition is varied depending on the container type, with a lower value for cadmium dioxide-rich glass container. The 40% cadmium dioxide-doped glass container provides more effective safety than the Cement + Bitumen container, according to the overall findings. In conclusion, the utilization of cadmium dioxide-doped glass material along with its high transparency and advanced material properties may be a significant and effective option in areas where concrete is required to assure the safety of nuclear materials.
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    Delving into the properties of nanostructured Mg ferrite and PEG composites: A comparative study on structure, electrical conductivity, and dielectric relaxation
    (Cell Press, 2023) El-Ghazzawy, Enas H.; Zakaly, Hesham M. H.; Alrowaily, Albandari W.; Saafan, Samia A.; Ene, Antoaneta; Abo-aita, Nagat M.; Darwish, Moustafa A.
    Magnesium ferrite (MgFe2O4) and polyethylene glycol (PEG) are materials known for their versatility in various applications. This study presents a comprehensive comparative analysis of the electrical conductivity and dielectric relaxation of nanostructured MgFe2O4 and its composites with PEG. Through experimentation, it was observed that incorporating PEG into MgFe2O4 did not lead to a high relative observed decrease or increase in electrical conductivity at room temperature. The study revealed that the composites maintained stable electrical behavior at room temperature, with a dielectric constant value of around 9 and a loss tangent value of around 0.1 at high frequency (around 7 MHz). The electron-hole hopping mechanism was identified as the underlying cause for the strong dielectric dispersion with frequency. The low dielectric loss and conductivity of the MgFe2O4 and PEG/ferrite composites make them promising candidates for high-frequency switching applications and microelectronic devices, particularly in scenarios where negligible eddy currents are essential. Additionally, complex impedance data analysis demonstrated that the capacitive and resistive properties of the composites are primarily attributed to grain boundary processes. This study provides a comprehensive analysis of the electrical and dielectric properties of MgFe2O4 and PEG composites and highlights their potential for many applications in materials science, particularly in electrical and electronic devices.
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    A detailed investigation on highly dense CuZr bulk metallic glasses for shielding purposes
    (De Gruyter Open, 2022) Tekin, Hüseyin Ozan; Almisned, G.; Susoy, Gülfem; Zakaly, Hesham M.H.; Issa, Shams A.M.; Kılıç, Gökhan; Rammah, Yasser Saad; Lakshminarayana, Gandham; Ene, Antoaneta
    Gamma-ray shielding properties of eight different metallic glasses based on CuxZr100-x: x = 35 (Cu35Zr65) - 70 (Cu70Zr30) were determined using Monte Carlo simulations and Phy-X/PSD software. A typical gamma-ray transmission setup has been modeled in MCNPX Monte Carlo code. The general trend of the linear attenuation coefficients (?) was reported as (?)Cu35Zr65 < (?)Cu40Zr60 < (?)Cu45Zr55 < (?)Cu50Zr50 < (?)Cu55Zr45 < (?)Cu60Zr40 < (?)Cu65Zr35 [removed] (MFP,HVL)Cu40Zr60 > (MFP,HVL)Cu45Zr55 > (MFP,HVL)Cu50Zr50 > (MFP,HVL)Cu55Zr45 > (MFP,HVL)Cu60Zr40 > (MFP,HVL)Cu65Zr35 > (MFP,HVL)Cu70Zr30 for all photon energy range. The Cu70Zr30 sample showed maximum values of both the effective conductivity (C eff) and effective electron density (N eff). In addition, the Cu70Zr30 sample has minimum exposure and energy absorption buildup factor (EBF and EABF) values at all studied gamma-ray energies. The results revealed that the Cu70Zr30 sample has superior attenuation properties among all studied samples. © 2022 Huseyin Ozan Tekin et al., published by De Gruyter.
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    Determination of gamma-ray transmission factors of WO3-TeO2-B2O3 glasses using MCNPX monte carlo code for shielding and protection purposes
    (DE GRUYTER POLAND SP Z O O, 2022) Almisned, Ghada; Susoy, Gülfem; Kılıç, Gökhan; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan; Baykal, Duygu Şen
    The aim of this study is to assess the individual gamma-ray transmission factors (TFs) and some fundamental gamma-ray attenuation properties of several types of glasses based on WO3-TeO2-B2O3 glasses system. MCNPX (version 2.7.0) is used for the calculation of TFs. Other critical parameters are determined using the Phy-X/PSD program. To determine the TFs of studied glasses, several medical radioisotopes are determined along with their characteristic gamma-ray energies. The superior values for the investigated parameters are found in glass sample S6. Furthermore, the exposure build-up factor and energy absorption build-up factor values for glass sample S6 were the lowest. S6 glass sample with the chemical composition 0.03833B + 0.26075O + 0.11591Zn + 0.52783Te + 0.05718W and a density of 3.3579 g/cm(3) is found to have exceptional gamma-ray attenuation qualities, according to our findings. It can be concluded that the prospective attributes of WO3-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.
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    Diagnostic and therapeutic radioisotopes in nuclear medicine: Determination of gamma-ray transmission factors and safety competencies of high-dense and transparent glassy shields
    (DE GRUYTER POLAND SP Z O O, 2022) Erdemir, Rabiye Uslu; Kılıç, Gökhan; Baykal, Duygu Şen; Almisned, Ghada; Issa, Shams A. M.; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan
    We present the findings of an extensive examination on newly designed CdO-rich and transparent glass shields for nuclear medicine facilities in lieu of traditional and unfavorable materials, such as lead and concrete. Gamma-ray transmission factors of newly designed glass shields are determined using a variety of diagnostic, therapeutic, and research radioisotopes, including Ga-67, Co-57, In-111, Tl-201, Tc-99m, Cr-51, I-131, Co-58, Cs-137, Ba-133, and Co-60. A general-purpose Monte Carlo code MCNPX (version 2.7.0) is used to determine the attenuation parameters of different material thicknesses. Next, the findings are compared using a standard concrete shielding material. The results indicate that adding more CdO to the glass composition improves the overall gamma-ray attenuation properties. As a result, among the heavy and transparent glasses developed, the C40 sample containing 40% CdO exhibited the best gamma-ray absorption properties against all radioisotopes. Furthermore, the gamma-ray absorption characteristics of this created high-density glass were shown to be better to those of a standard and heavy concrete sample. It can be concluded that the newly developed CdO-rich and transparent glass sample may be used in medical radiation fields where the radioisotopes examined are used in daily clinical and research applications.
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    Dual Impacts of Bi2O3/B2O3 Substitution on Mechanical and Attenuation Properties of Zinc-Bismuth-Borate Ternary Glasses for Diagnosis ?-Rays Shielding Materials Application
    (Springer, 2023) Zakaly, Hesham M. H.; Tekin, H. O.; Issa, A. M. Shams; Alrowaily, Albandari W.; Ene, Antoaneta; Rammah, Y. S.
    Investigations have been made on the mechanical and gamma-ray attenuation properties of the zinc bismuth-borate ternary glass system with the chemical formula (70-x)Bi2O3-xB(2)O(3)-30ZnO, where x = 20 (S1), 25 (S2), 30 (S3), 40 (S4), 45 (S5), and 50 (S6) mol%. Makishima-Mackenzie model and Phy-X/PSD software were used to accomplish this goal. Our research showed that the packing density (Vt) and dissociation energy (Gt) values reduced from S1 glass sample (with B2O3 = 20 mol% and Bi2O3 = 50 mol%) to S6 glass sample (with B2O3 = 50 mol% and Bi2O3 = 20 mol%), respectively, from 0.522 to 0.352 and from 31.53 kJ/cm(3) to 26.97 kJ/cm(3). By increasing the amount of B2O3 in the glasses, the efficiency of their mechanical features was reduced. The S1 glass sample's linear (mu) and mass attenuation (mu(m)) coefficients had the highest values among the glass materials examined, i.e., (mu, mu(m))(S6) < (mu, mu(m))(S5) < (mu, mu(m))(S4) < (mu, mu(m))(S3) < (mu, mu(m))(S2) < (mu, mu(m))(S1). The S1 glass sample exhibits the lowest values for half value layer (T-0.5) and mean free path (lambda) of all the examined glasses. Consequently, (T-0.5, lambda )(S6) > (T-0.5, lambda )(S5) > (T-0.5, lambda )(S4) > (T-0.5, lambda )(S3) > (T-0.5, lambda )(S2) > (T-0.5, lambda )(S1). The analyzed glasses' effective atomic numbers (Z(eff)) follow the same trend for mass and linear attenuation coefficients. Our results show that the values of exposure (EBF) and energy absorption (EABF) accumulation factors decreased with increasing Bi2O3 and lowering B2O3 reinforcement for all mean free path values (i.e., from 0.5 to 40 mfp). Results show that of all the glasses under study, the S1 glass sample has the best gamma-ray shielding properties.
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    Electrospun PVDF/Barium hexaferrite fiber composites for enhanced electromagnetic shielding in the X-band range
    (Elsevier, 2023) Salem, M. M.; Kenawy, El-Refaie; Zakaly, Hesham M. H.; Ene, Antoaneta; Azaam, Mohamed M.; Edries, Tarek B.; Zhou, Di
    In the contemporary, digitally-driven era, the prevalence of electronic devices has drastically escalated electromagnetic (EM) pollution levels, marking a significant environmental challenge. Electrospun fiber composites of polyvinylidene fluoride (PVDF) and Barium hexaferrite (BHF) were analyzed for their potential usage in X -band electromagnetic shielding applications (EMSAs). Pure PVDF and BHF-PVDF fiber composite were manufactured by needleless electrospinning. X-ray diffraction (XRD), Fourier-transform infrared spectroscopy (FTIR), scanning electron microscopy (SEM), thermogravimetric analysis (TGA), vibrating sample magnetometer (VSM), and EM measurements utilizing a vector network analyzer (VNA) are all used to describe the prepared samples. The XRD and FTIR analyses confirmed the successful incorporation of BHF into the PVDF matrix. The results show that adding PVDF to BHF in fiber form enhances the reflection loss (RL), indicating improved electro-magnetic shielding effectiveness (EMSE). The SEM analysis revealed that the fiber composite had a uniform fiber diameter distribution. In contrast, the TGA analysis demonstrated good thermal stability of the fiber composite. Polymer samples were evaluated to enhance gamma radiation and neutron particle attenuation. MCNP5 and Phy-X/PSD software were used to study semi-crystalline fluorocarbon polymer (PVDF) and barium hex ferrite BaFe12O19 (30 wt%) with PVDF (70 wt%). The MCNP5 programme simulated 0.015-15 MeV radiation atten-uation. Additionally, the Phy-X/PSD programme verified the simulated mu values for the chosen Mxenes materials. The MCNP-5 code and Phy-X/PSD results were agreed. The linear attenuation coefficients for the polymer samples ranged from 3.166 to 0.032 cm2.g ? 1 for PVDF and from 73.960 to 0.113 cm2.g ? 1 for PVDF and BHF-PVDF Fiber at photon energies from 0.015 to 15 MeV. Overall, the electrospun fiber composite of PVDF and BHF particles shows promise for EMSAs in the X-band range. The enhanced RL observed in our study suggests that these fiber composites could be used to protect against electromagnetic radiation (EMR) from electronic devices, which is increasingly concerning in today's modern society.
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    Exploring the Radioprotective Indium (III) Oxide Screens for Mammography Scans Using a Three-Layer Heterogeneous Breast Phantom and MCNPX: A Comparative Study Using Clinical Findings
    (Mdpi, 2023) ALMisned, Ghada; Elshami, Wiam; Kilic, Gokhan; Ilik, Erkan; Rabaa, Elaf; Zakaly, Hesham M. H.; Ene, Antoaneta
    Background: During mammography, a lead-acrylic protective screen is recommended to reduce radiation exposure to the unexposed breast. Objectives: This research study aimed to construct an Indium-(III)-oxide-rich tellurite-glass screen (TZI8) and compare its performance to that of lead acrylic. Materials and Methods: A three-layer heterogeneous-breast phantom was developed, using the MCNPX (version 2.7.0) Monte Carlo code. An MCNPX-simulation geometry was designed and implemented, using the lead-acrylic and TZI8 shielding screens between the right and left breast. Next, the reliability of the phantom and the variations in absorption between the lead-acrylic and TZI8 glass were investigated. Results: The findings show that the TZI8-protective-glass screen offers significantly greater radioprotection than the lead-acrylic material. The quantity of total dose absorbed in the unexposed breast was much lower for TZI8 than for lead-based acrylic. The TZI8-glass screen gives about 60% more radioprotection than the lead-acrylic screen. Conclusion: Considering the toxic lead in the structure that may be hazardous to the human tissues, the TZI8-glass screen may be used in mammography examination to provide greater radioprotection than the lead-acrylic screen, in order to greatly reduce the dose to the unexposed breast.
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    A focusing study on radioprotective and antioxidant effects of Annona muricata leaf extract in the circulation and liver tissue: clinical and experimental studies
    (De Gruyter Open Ltd, 2022) Elmas, Özlem; Şahin, Havva Hande Keser; Güven, Berrak; Abuzaid, Mohamed M.; Elshami, Wiam; Almisned, Ghada; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan
    Objectives: This study investigates the effect of Annona muricata (AM) leaf extract against irradiation-induced damage by the evaluation of hepatic tissue and the levels of oxidative and inflammatory stress in the circulation. Methods: An experimental study with 37 female Wistar albino rats randomized into four groups (controls and three intervention groups) was performed. The first interventional group (group 2) received 300 mg/kg of AM leaf extract by oral gavage once a day for 9 days, group 3 received a single dose of whole-body radiation (8.3 Gy) after a 9-day oral gavage treatment with saline, and the last group received the same irradiation of 8.3 Gy after being treated with 300 mg/kg of AM leaf extract by oral gavage once a day for 9 days. Results: Radiation was found to elevate reactive oxygen species parameters, and AM administration before irradiation was found to decrease total oxidant status (TOS), increase caspase 9, and improve hepatic damage when compared with the group that received only irradiation. Conclusion: The damage caused by irradiation may be ameliorated by the use of the AM extract, which appears to be effective in preventing oxidative stress and inflammatory activity.
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    Gamma, neutron, and heavy charged ion shielding properties of Er3+-doped and Sm3+-doped zinc borate glasses
    (De Gruyter Open Ltd, 2022) Tekin, Hüseyin Ozan; Almisned, Ghada; Zakaly, Hesham M.H.; Zamil, Abdallah; Khoucheich, Dalia; Bilal, Ghaida; Al-Sammarraie, Lubna; Issa, Shams A.M.; Al-Buriahi, Mohammed Sultan; Ene, Antoaneta
    This study aimed to investigate the nuclear radiation shielding properties of erbium (Er)-reinforced and samarium (Sm)-reinforced borate glasses. In the 0.015-15 MeV photon energy range, attenuation coefficients, as well as half-value layer tenth-value layers, and the mean-free path have been calculated. Additionally, effective, and equivalent atomic numbers, effective atomic weight, electron density, and exposure and energy absorption build-up factors were also calculated. To evaluate the overall nuclear radiation attenuation competencies of Er-rich and Sm-rich glasses, effective removal cross-section values for fast neutrons and projected range/mass stopping power values for alpha and proton particles were also determined. The glass sample BZBEr2.0 had the highest linear and mass attenuation coefficients (? and ?m), effective conductivity (Ceff), the effective number of electrons (Neff), and effective atomic number (Zeff) values as well as the lowest half-value layer (T1/2), tenth value layers (T1/10), mean free path (?), exposure build-up factor, and energy absorption build-up factor values. ?m values were reported as 2.337, 2.556, 2.770, 2.976, 2.108, 2.266, 2.421, 2.569, and 2.714 for BZBEr0.5, BZBEr1.0, BZBEr1.5, BZBEr2.0, BZBSm0.0, BZBSm0.5, BZBSm1.0, BZBSm1.5, and BZBSm2.0 glass samples at 0.06 MeV, respectively. The results showed that Er has a greater effect than Sm regarding the gamma-ray shielding properties of borate glasses. The results of this investigation could be used in further investigations and added to older investigations with the same aim, to aid the scientific community in determining the most appropriate rare-earth additive, to provide adequate shielding properties based on the requirement. © 2022 Huseyin Ozan Tekin et al., published by De Gruyter.
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    Graphene-bioactive glass composites: Structural, Vickers hardness, and gamma-ray attenuation characteristics
    (Frontiers Media Sa, 2023) Deliormanli, Aylin M.; ALMisned, Ghada; Ene, Antoaneta; Tekin, H. O.
    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/cm(3). 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.