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Öğe A benchmarking analysis on different rubber materials: towards customisation of lightweight and effective radiation protection solutions for aerospace and electronic applications(Springer, 2024) Alkarrani, Hessa; ALMisned, Ghada; Tekin, Hüseyin OzanThis study examines the efficacy of rubber, a non-toxic hydrocarbon polymer, as a shielding material against gamma rays and neutrons. We analyse four types of rubbers: Neoprene, Butyl, Natural, and Silicone, using computational methods and Monte Carlo simulations via MCNP (version 6.3) to evaluate their gamma ray and neutron shielding parameters. Notably, Neoprene, enhanced with chlorine, shows superior gamma ray attenuation capabilities with a mass attenuation coefficient (MAC) of 760.446 cm2/g at 0.015 MeV, indicating its potential as an effective material for gamma ray shielding applications. Conversely, Butyl rubber, with its high hydrogen content, exhibits exceptional neutron attenuation properties, with the highest Sigma R value of 11.861 1/cm, making it a preferred choice for neutron shielding. This investigation underscores the versatility and environmental benefits of rubber materials in radiation protection, highlighting their potential as lightweight, customisable and sustainable alternatives to conventional shielding substances like lead. Our findings reveal prominent advantages of Neoprene for gamma ray shielding and Butyl rubber for neutron protection, contributing to the development of safer, more effective radiation protection solutions.Öğe A benchmarking analysis on different rubber materials: towards customisation of lightweight and effective radiation protection solutions for aerospace and electronic applications(Springer nature, 2025) Alkarrani, Hessa; Almisned, Ghada; Tekin, Hüseyin OzanThis study examines the efficacy of rubber, a non-toxic hydrocarbon polymer, as a shielding material against gamma rays and neutrons. We analyse four types of rubbers: Neoprene, Butyl, Natural, and Silicone, using computational methods and Monte Carlo simulations via MCNP (version 6.3) to evaluate their gamma ray and neutron shielding parameters. Notably, Neoprene, enhanced with chlorine, shows superior gamma ray attenuation capabilities with a mass attenuation coefficient (MAC) of 760.446 cm2/g at 0.015 MeV, indicating its potential as an effective material for gamma ray shielding applications. Conversely, Butyl rubber, with its high hydrogen content, exhibits exceptional neutron attenuation properties, with the highest Sigma R value of 11.861 1/cm, making it a preferred choice for neutron shielding. This investigation underscores the versatility and environmental benefits of rubber materials in radiation protection, highlighting their potential as lightweight, customisable and sustainable alternatives to conventional shielding substances like lead. Our findings reveal prominent advantages of Neoprene for gamma ray shielding and Butyl rubber for neutron protection, contributing to the development of safer, more effective radiation protection solutions.Öğe A comparative investigation on mechanical, gamma-ray and neutron shielding properties of some iron and boron containing concretes samples for nuclear safety applications(Pergamon-elsevier science LTD, 2024) Almisned, Ghada; Susoy, Gülfem; Baykal, Duygu Şen; Tekin, Hüseyin OzanThis study explores the gamma-ray and neutron shielding properties of fourteen different concrete samples, each tailored with varying percentages of Boron Carbide, Iron, and Iron Boride. Using the MCNP 6.3 Monte Carlo code, we calculated transmission factors for photon energies of 0.662 MeV, 1.1732 MeV, and 1.3325 MeV, and analyzed the impact of concrete thickness on shielding efficacy. Additionally, the Phy-X/PSD software was used to compute critical parameters such as linear and mass attenuation coefficients, half-value layer, tenth-value layer, mean free path, and fast neutron removal cross-section to gain a comprehensive understanding of each material's shielding capabilities. Our findings indicate that adding iron to the concrete matrix significantly enhances its attenuation properties, with the 20%Fe+80%Concrete sample outperforming all others. This composition demonstrated the lowest transmission factors across all tested energies and thicknesses, indicating superior photon attenuation. Moreover, the 20%Fe+80% Concrete exhibited the highest fast neutron removal cross-section, making it highly effective for environments requiring neutron shielding. In addition to the shielding properties, we analyzed the Elastic (Young's) Modulus of the concrete samples to understand their mechanical properties. Standard Concrete had an Elastic Modulus of 261.24 GPa, while the introduction of boron carbide significantly enhanced the Elastic Modulus, with pure boron carbide concrete exhibiting a value of 518.88 GPa. Concrete samples with varying percentages of boron carbide (5%, 10%, 15%, and 20%) showed a progressive increase in Elastic Modulus, indicating that higher proportions of boron carbide consistently enhance the material's stiffness. Conversely, concrete samples with iron boride and iron showed slight reductions in Elastic Modulus. It can be concluded that the boron carbide enhances stiffness, iron and iron boride provide a balance between stiffness and other properties. In conclusion, the 20%Fe+80%Concrete is a standout material that could greatly improve radiation shielding, offering major benefits.Öğe A comparative investigation on mechanical, gamma-ray and neutron shielding properties of some iron and boron containing concretes samples for nuclear safety applications(Elsevier Ltd, 2024) ALMisned, Ghada; Susoy, Gülfem; Sen Baykal, Duygu; Tekin, Hüseyin OzanThis study explores the gamma-ray and neutron shielding properties of fourteen different concrete samples, each tailored with varying percentages of Boron Carbide, Iron, and Iron Boride. Using the MCNP 6.3 Monte Carlo code, we calculated transmission factors for photon energies of 0.662 MeV, 1.1732 MeV, and 1.3325 MeV, and analyzed the impact of concrete thickness on shielding efficacy. Additionally, the Phy-X/PSD software was used to compute critical parameters such as linear and mass attenuation coefficients, half-value layer, tenth-value layer, mean free path, and fast neutron removal cross-section to gain a comprehensive understanding of each material's shielding capabilities. Our findings indicate that adding iron to the concrete matrix significantly enhances its attenuation properties, with the 20%Fe+80%Concrete sample outperforming all others. This composition demonstrated the lowest transmission factors across all tested energies and thicknesses, indicating superior photon attenuation. Moreover, the 20%Fe+80% Concrete exhibited the highest fast neutron removal cross-section, making it highly effective for environments requiring neutron shielding. In addition to the shielding properties, we analyzed the Elastic (Young's) Modulus of the concrete samples to understand their mechanical properties. Standard Concrete had an Elastic Modulus of 261.24 GPa, while the introduction of boron carbide significantly enhanced the Elastic Modulus, with pure boron carbide concrete exhibiting a value of 518.88 GPa. Concrete samples with varying percentages of boron carbide (5%, 10%, 15%, and 20%) showed a progressive increase in Elastic Modulus, indicating that higher proportions of boron carbide consistently enhance the material's stiffness. Conversely, concrete samples with iron boride and iron showed slight reductions in Elastic Modulus. It can be concluded that the boron carbide enhances stiffness, iron and iron boride provide a balance between stiffness and other properties. In conclusion, the 20%Fe+80%Concrete is a standout material that could greatly improve radiation shielding, offering major benefits. © 2024 Elsevier LtdÖğe A critical assessment of the mechanical strength and radiation shielding efficiency of advanced Concrete composites and Vanadium Oxide-Glass container for enhanced nuclear waste management(Elsevier B.V., 2024) Tekin, Hüseyin Ozan; ALMisned, Ghada; Kılıç, Gökhan; İlik, Erkan; Susoy, Gülfem; Elshami, Wiam E.; Issa, BasharThe nuclear industry produces large quantities of low, intermediate, and high levels of radioactive waste, all of which require safe management during both transport and storage. This study evaluates the radiation shielding effectiveness and mechanical properties of four distinct container materials: Pb Composite Glass, 0.5 Cement-0.5 Bitumen, Concrete (Steel-Magnetite), and C9 (BCBV0.5) Vanadium Oxide-Glass. Using Monte Carlo simulations and theoretical methods, we determined the Transmission Factors (TF) and Half-Value Layers (HVL) for each material. The TF indicates the effectiveness of a material in attenuating radiation, calculated by the ratio of gamma rays exiting the material to those entering it. Lower TF values signify better radiation shielding. The HVL is the thickness of material required to reduce the intensity of gamma rays by half, with lower HVL values indicating more effective shielding. Concrete (Steel-Magnetite) demonstrated superior performance with the lowest TF values (e.g., 1.0 × 10-1 at 0.662 MeV and 1 cm thickness) and HVL values (e.g., 2.5 cm at 1.3325 MeV), alongside a high elastic modulus of 163.15 GPa, indicating its robustness for high-energy gamma-ray applications. Pb Composite Glass also showed strong performance with a TF of 9.5 × 10-2 at 0.662 MeV and 1 cm thickness, an HVL of 2.0 cm at 0.662 MeV, and an elastic modulus of 41.54 GPa. The C9 (BCBV0.5) Vanadium Oxide-Glass, with an elastic modulus of 73.79 GPa, outperformed the 0.5 Cement-0.5 Bitumen mixture in both TF (e.g., 1.15 × 10-1 at 0.662 MeV and 1 cm thickness) and HVL (e.g., 4.2 cm at 1.1732 MeV) measurements, highlighting its potential as a more effective alternative. It can be concluded that C9 (BCBV0.5) Vanadium Oxide-Glass presents promising properties for future advancements in radiation protection, warranting further research and optimization. © 2024 The Author(s)Öğe 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; Baykal, Duygu Şen; Kılıç, Gökhan; İlik, Erkan; Zakaly, Hesham M.H.; Ene, Antoaneta; Tekin, Hüseyin OzanWe examine the nuclear safety properties of a newly designed cadmium oxide-rich glass container for nuclear material to a bitumen-reinforced concrete container. Individual transmission factors, detector modelling, 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 dioxide-rich 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. Copyright © 2022 ALMisned, Baykal, Kilic, Ilik, Zakaly, Ene and Tekin.Öğe A first-time fusion of TiNbWMoZrOx high entropy oxide (HEO) with zinc-tellurite glass: Toward superior physical properties(Elsevier B.V., 2024) Kılıç, Gökhan; Güler, Ömer; Kavaz, Esra; İlik, Erkan; Güler, Seval Hale; ALMisned, Ghada; Tekin, Hüseyin OzanWhile numerous oxide additives have traditionally been employed to enhance the radiation shielding capabilities of glasses, the unique attributes of high-entropy oxides (HEOs), a group of materials acclaimed in contemporary material science for their distinctive properties have remained unexamined in this specific area. This novel study explores the enhancement of radiation shielding properties in zinc-tellurite glasses through the integration of TiNbWMoZrOx High Entropy Oxides (HEO). Utilizing advanced synthesis techniques, including mechanical alloying and oxidation, the research successfully incorporates HEOs into glass matrices, aiming to improve gamma-ray and neutron attenuation. Characterization through X-ray diffraction (XRD), scanning electron microscopy (SEM), and X-ray photoelectron spectroscopy (XPS) confirms the uniform distribution and structural integrity of the HEOs within the glasses. The synthesis of glass samples with a base structure suitable for the molar composition of 25ZnO.75TeO2 (mol%) and glass samples doped with TiNbWMoZrOx (HEO) was carried out using the traditional high-temperature melting and annealing method. The outcomes demonstrate a concentration-dependent increase in shielding efficacy, particularly highlighting the superior performance of glasses doped with 4 mol% of TiNbWMoZrOx (HEC2–4), which exhibit significantly enhanced mass attenuation coefficients, lower half-value layers, and higher effective atomic numbers. This indicates the effective role of HEOs in boosting radiation protection capabilities. Comparative analysis with traditional shielding materials showcases the HEC2–4 glasses' competitive advantage, underlining their potential as a versatile shielding solution. It can be concluded that incorporating TiNbWMoZrOx high entropy oxides into zinc-tellurite glasses significantly augments their radiation shielding properties, offering a novel approach for enhancing protection against gamma-ray and neutron in various applications. © 2024 Elsevier B.V.Öğe An assessment of microstructure, dentinal tubule occlusion and X-ray attenuation properties of Nd: YAG laser-enhanced titanium-doped phosphate glass and nano-hydroxyapatite pastes (vol 130, 313, 2024)(Springer heidelberg, 2024) Abou Neel, Ensanya A.; El-Damanhoury, Hatem M.; Hossain, Kazi M. Zakir; Alawadhi, Hussain; AlMisned, Ghada; Tekin, Hüseyin OzanAn assessment of microstructure, dentinal tubule occlusion and X-ray attenuation properties of Nd: YAG laser-enhanced titanium-doped phosphate glass and nano-hydroxyapatite pastes (vol 130, 313, 2024)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 Assessing the efficacy of some heavy-metal infused concrete mixtures in gamma-ray and neutron shielding applications(Pergamon-elsevier science, 2024) Alkarrani, Hessa; Almisned, Ghada; Tekin, Hüseyin OzanThis study examines the radiation shielding properties of sixteen diverse concrete types encompassing both gamma-ray and neutron radiation. Concrete, a widely used material due to its low cost, high density, and efficient shielding capabilities, is investigated to determine how its varying compositions impact its ability to attenuate ionizing radiation. Utilizing the Phy-X/PSD software, the research analyses key parameters like mass attenuation coefficients, linear attenuation coefficients, and half-value layers, among others, to assess each concrete type's shielding efficiency. The findings reveal that concretes containing heavy metals such as iron and barium exhibit enhanced performance in absorbing photons, thus providing superior protection against radiation. Iron-Portland concrete demonstrated a high density of 5.80 g/cm3 and exhibited a mass attenuation coefficient (MAC) of 35.14 cm2/g at 0.1 MeV, significantly higher than MAC of ordinary concrete (i.e., 17.24 cm2/ g). Significantly, Iron-Portland and Barite Concrete are highlighted for their exceptional shielding abilities, with Iron-Portland showing a fast neutron removal cross-section (Sigma R) of 14.29 cm-1, compared to 11.11 cm-1 for ordinary concrete. It can be concluded that the high elemental mass fraction of iron (88.12 wt%) in Iron-Portland concrete, along with its significant density of 5.80 g/cm3, makes it the most advantageous for gamma-ray and neutron shielding applications due to its superior absorption and attenuation capabilities.Öğe 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 OzanWe 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.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 Bismuth(III) oxide and boron(III) oxide substitution in bismuth-boro-zinc glasses: a focusing in nuclear radiation shielding properties(ELSEVIER GMBH, 2023) Almisned, Ghada; Bilal, Ghaida; Şen Baykal, Duygu; Ali, Fatema T.; Kılıç, G.; Tekin, Hüseyin OzanDoping 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.Öğe Boron nitride nanosheet-reinforced WNiCoFeCr high-entropy alloys: the role of B4C on the structural, physical, mechanical, and radiological shielding properties(Springer Science and Business Media Deutschland GmbH, 2022) Kavaz, Esra; Gül, Ali Oktay; Başgöz, Öyküm; Güler, Ömer; Almisned, Ghada; Bahçeci, Ersin; Güler, Seval Hale; Tekin, Hüseyin OzanThe synthesis and extensive characterization of newly developed boron nitride nanosheet (BNNSs)-reinforced WNiCoFeCr high-entropy alloys (HEAs) are presented. The influence of B4C on the structural, physical, mechanical, and nuclear shielding characteristics of synthesized HEAs has been widely examined in terms of its monotonic effects on the behavior changes. The internal morphology and structural characteristics of the fabricated composites are first investigated using X-ray diffraction, scanning electron microscopy, and energy-dispersive spectroscopy. Wear testing is used to determine the coefficient of friction as a function of sliding distance. Experimental gamma ray and neutron setups are created to determine their shielding characteristics against nuclear radiation. Finally, the shielding characteristics of nuclear radiation for gamma ray and fast neutrons are compared extensively to those of many existing and new-generation shielding materials. Among the examined samples, the S2 sample with B4C and BNNSs reinforcement had the greatest mechanical characteristics. Our findings imply that increasing B4C directly contributes to the shielding qualities of nuclear radiation. The B4C created in the structure of BNNSs contributes to the overall properties of HEAs, which are crucial for nuclear applications, since HEAs are being examined as a component of future nuclear reactors. Additionally, B4C is a very versatile material that may be used in circumstances where mechanical and nuclear shielding properties need to be enhanced for a variety of radiation energies. © 2022, The Author(s), under exclusive licence to Springer-Verlag GmbH, DE part of Springer Nature.Öğe Boron nitride nanosheet-reinforced WNiCoFeCr high-entropy alloys: the role of B4C on the structural, physical, mechanical, and radiological shielding properties (vol 128, 694, 2022)(SPRINGER HEIDELBERG, 2022) Kavaz, Esra; Gül, Ali Oktay; Başgöz, Öyküm; Güler, Ömer; Almisned, Ghada; Bahçeci, Ersin; Güler, Seval Hale; Tekin, Hüseyin OzanNo Abstract Available.Öğe Calculation of gamma-ray buildup factors for some medical materials(ICE Publishing, 2022) Çelen, Yonca Yahşi; Sarıhan, Mucize; Almisned, Ghad; Tekin, Hüseyin Ozan; Ekmekçi, İsmailIn recent years, novel materials with protective qualities against ionizing radiation have been discovered. Important concepts include the continued use of X-rays for diagnosis and treatment, particularly in the radiological energy range, as well as the calculation of the radiation attenuation properties of such materials, the build-up factor, and the attenuation coefficients. Radiation shielding is characterized by parameters such as linear attenuation coefficient (LAC, cm-1),.equivalent atomic number (Zeq), exposure buildup factors (EBF) and exposure absorption buildup factors (EABF). Radiation is often employed in the diagnosis and treatment of cancer and accurately calculating the absorbed dosage during radiation treatment, which is one of the most popular cancer treatments. It relies on accurate modeling of the radiation beams administered to the patient and their interaction with the environment in which they are absorbed. In this research, the shielding characteristics of water, fat, and bone related to human tissue are investigated. Using Phy-X/PSD software, the equivalent atomic number (Zeq), exposure buildup factor (EBF), and energy absorption buildup factor (EABF) were determinedÖğe 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, AntoanetaThallium-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.Öğe CdO-rich quaternary tellurite glasses for nuclear safety purposes: Synthesis and experimental gamma-ray and neutron radiation assessment of high-density and transparent samples(Elsevier, 2022) Kılıç, Gökhan; Kavaz, Esra; İlik, Erkan; Almisned, Ghada; Tekin, Hüseyin OzanWe 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.Öğe Characterization of Ultramafic–Alkaline–Carbonatite complex for radiation shielding competencies: An experimental and Monte Carlo study with lithological mapping(Elsevier, 2022) Libeesh, N.K.; Naseer, K.A.; Arivazhagan, S.; El-Rehim, A.F.A.; ALMisned, G.; Tekin, Hüseyin OzanThe 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)Öğe 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 OzanWe 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.
