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Öğe 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.Öğe 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)Öğe 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 OzanThe 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.Öğe 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 GmbHÖğe 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, AntoanetaGamma-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.Öğe Experimental and FLUKA evaluation on structure and optical properties and ?-radiation shielding capacity of bismuth borophosphate glasses(Elsevier Ltd, 2022) Madbouly, A.M.; Sallam, O.I.; Issa, Shams A.M.; Rashad, M.; Hamdy, Amany; Tekin, Hüseyin Ozan; Zakaly, Hesham M.H.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. © 2022Öğe Fabrication of newly developed tungsten III-oxide glass family: Physical, structural, mechanical, radiation shielding effectiveness(Elsevier GmbH, 2022) Issa, Shams A.M.; Tekin, Hüseyin Ozan; Saudi, H.A.; Koubisy, M.S.I.; Zhukovsky, M.; Ali, Ahmed S.; Zakaly, Hesham M.H.A series of glasses based on the nominal composition of (Na2O)5 + (Al2O3)10 + (SiO2)(85+x)/2 + (CaO)(85+x)/2 + (WO3)x glasses system were produced utilizing the usual melt quenching process in this study. Experimental techniques and the FLUKA Monte Carlo algorithm were used to examine the properties of silicon-calcium glasses containing tungstate-III-oxide. For five glass structures identified according to (Na2O)5+(Al2O3)10+(SiO2)(85+x)/2+(CaO)(85+x)/2+(WO3)x (0 ?x ? 20 wt-%) glass composition, the impact of tungstate-III-oxide with ratios of (0 ?x ? 20 wtpercent) on radiation shielding characteristics of glasses was set. The densities of the produced glasses fluctuated between 2.847 g/cm3 and 3.122 g/cm3 when tungstate-III-oxide was substituted. The produced sample densities, which are important in assessing radiation shielding features, rose as the WO3 concentration increased, according to our first results. In addition, the structure of each sample was studied using FT-IR. FT-IR showed that when WO3 levels rose, the connection level increased, and the FT-IR spectra shifted to higher wavenumbers. The synthesis of WO3 in a glass matrix enhances the structural network by raising oxygen levels, which leads to the transition of SiO2 into - CaO. Elastic moduli and Ultrasonic velocities were found to rise as the ratio of WO3 in the generated samples increased. These two approaches were used to model linear and mass attenuation coefficients, photons-transmittance versus photon energy, radiation protection efficiency against photon energy, and absorber thickness (experimental and simulation). Based on the results, it can be stated that the w20 sample, which contains 20 wt%, will play the most effective function in radiation shielding. Increases in WO3 led in considerable increases in linear and mass attenuation coefficient values, which directly contribute to the development of the glass's radiation shielding characteristics. © 2022 Elsevier GmbHÖğe Fabrication, optical, structural, and gamma-ray attenuation properties of novel slag-waste glasses as superior shields: An exploring journey for waste to glass transformation(Elsevier GmbH, 2022) Issa, Shams A.M.; Zakaly, Hesham M.H.; Rashad, M.; Ali, Ahmed S.; Tekin, Hüseyin OzanWe present a comprehensive study on the transformation of municipal slug wastes into glass samples with exceptional gamma-ray attenuation capabilities that may be used in medical and industrial radiation applications to the benefit of society. The whole process is performed using an adsorbent developed by loading iron oxide and TiO2 on municipal solid waste melted slag. The loading is carried out through chemical reactions and high-temperature process. The oxidation of arsenite with a concentration of 100 mg L?1 is completed in 3 h. Next, the glass synthesis process is performed using well-known melt-quenching method. Structural, optical, and gamma-ray attenuation properties are determined using experimental and theoretical methods. Our findings showed that a wide hump centered at 2?= 30° with no indication of any precise peaks emerging in the crystalline phases and glasses under investigation have amorphous natures. Using several well-known radioisotope energies, the half-value layers of slow waste glasses are determined. The 11-G sample demonstrated the greatest gamma-ray attenuation characteristics among the manufactured glass samples. The 11-G sample's half layer values are then compared to those of comparable glass, concrete, and polymer shields available in the literature. The results demonstrated that 11-G is clearly better than the other shield types. It can be concluded that some other novel materials with superior shielding properties may be manufactured using more thoroughly separating techniques in terms of determining the best conditions for this type of superior materials. It can be also concluded that some other characterization phases may be conducted in terms of identifying the undiscovered properties of the current samples towards better understanding of slug-waste based glasses and their potential applications.Öğe 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, AntoanetaThis 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.Öğe Heavy metal oxide (HMO) glasses as an effective member of glass shield family: A comprehensive characterization on gamma ray shielding properties of various structures(Elsevier Editora Ltda, 2022) Tekin, Hüseyin Ozan; Susoy, Gülfem; Issa, Shams A.M.; Ene, Antoaneta; ALMisned, Ghada; Rammah, Y.S.; Ali Fatema, T.; Algethami, Merfat; Zakaly, Hesham M.H.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)Öğe Heavy metal oxide added glassy portable containers for nuclear waste management applications: in comparison with reinforced concrete containers(Elsevier Ltd., 2022) Tekin, Hüseyin Ozan; Rainey, Clare; Almisned, Ghada; Issa, Shams A.M.; Akkuş, Baki; Zakaly, Hesham M.H.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.Öğe Nuclear shielding performances of borate/sodium/potassium glasses doped with Sm3+ ions(Elsevier Editora Ltda, 2022) Zakaly, Hesham M.H.; Rammah, Y.S.; Tekin, Hüseyin Ozan; Ene, Antoaneta; Badawi, Ali; Issa, Shams A.M.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 (?) 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)Öğe A rapid and direct method for half value layer calculations for nuclear safety studies using MCNPX Monte Carlo code(Korean Nuclear Society, 2022) Tekin, Hüseyin Ozan; Almisned, Ghada; Issa, Shams A.M.; Zakaly, Hesham M.H.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 SocietyÖğe Synergistic effect of boron nitride and graphene nanosheets on behavioural attitudes of polyester matrix: Synthesis, experimental and Monte Carlo simulation studies(Elsevier Ltd, 2022) Başgöz, Öyküm; Güler, Seval Hale; Güler, Ömer; Canbay, Canan A.; Zakaly, Hesham M.H.; Issa, Shams A.M.; Almisned, Ghada; Tekin, Hüseyin OzanWe 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. © 2022Öğe Synthesis and structural, electrical, optical, and gamma-ray attenuation properties of ZnO-multi-walled carbon nanotubes (MWCNT) composite separately incorporated with CdO, TiO2, and Fe2O3(Elsevier Ltd, 2022) Başgöz, Öyküm; Güler, Ömer; Evin, Ertan; Yavuz, Cağdaş; Almisned, Ghada; Issa, S.A.M.; Zakaly, Hesham M.H.; Tekin, Hüseyin OzanIn 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. © 2022 Elsevier Ltd and Techna Group S.r.l.Öğe Transmission factor (TF) behavior of Bi2O3–TeO2–Na2O–TiO2–ZnO glass system: A Monte Carlo simulation study(MDPI, 2022) Tekin, Hüseyin Ozan; Almisned, Ghada; Susoy, Gülfem; Ali, Fatema T.; Baykal, Duygu Şen; Ene, Antoaneta; Issa, Shams A.M.; Rammah, Yasser S.; Zakaly, Hesham M.H.The main objective of the present work was to assess the gamma radiation shielding competencies and gamma radiation transmission factors (TFs) for some tellurite glasses in the form of Bi2O3–TeO2–Na2O–TiO2–ZnO. MCNPX general-purpose Monte Carlo code (version 2.6.0) was utilized for the determination of TF values at various well-known radioisotope energies for different glass thicknesses from 0.5 cm to 3 cm. Moreover, some important gamma ray shielding properties were also determined in the 0.015–15 MeV energy range. The results show that glass densities were improved from 5.401 g/cm3 to 6.138 g·cm3 as a function of Bi2O3 increment in the glass composition. A S5 glass sample with the maximum Bi2O3 additive was reported with superior gamma ray shielding properties among the studied glasses. It can be concluded that Bi2O3 can be used as a functional tool in terms of improving glass density and, accordingly, gamma ray shielding attenuation properties of tellurite glasses, where the role Bi2O3 is also critical for other material properties, such as structural, optical, and mechanical. © 2022 by the authors. Licensee MDPI, Basel, Switzerland.