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Yazar "Alkarrani, Hessa" seçeneğine göre listele

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    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 Ozan
    This 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.
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    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 Ozan
    This 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.
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    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 Ozan
    This 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.
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    A closer-look on W and Pb alloys: In-depth evaluation in elastic modulus, gamma-ray, and neutron attenuation for critical applications
    (Elsevier Science Sa, 2024) Almisned, Ghada; Susoy, Gulfem; Sen Baykal, Duygu; Alkarrani, Hessa; Guler, Omer; Tekin, H. O.
    This investigation assesses the gamma -ray and neutron attenuation properties of various alloys, including Pb90Cu10, A5, Manganin-R, Cu0.2Ag0.8, SA4, and W -based, to uncover efficient and cost-effective radiation shielding materials. Our study centers on alloys featuring elements such as lead, molybdenum, silver, and tungsten, selected for their unique protective qualities against radiation. Employing computational methods to evaluate critical parameters like mass attenuation coefficients, half -value layers, linear attenuation coefficients, and effective atomic numbers, transmission factor, we found the W -based alloy to exhibit exceptional shielding properties, primarily due to its tungsten content. Interestingly, this alloy also demonstrated the highest elastic modulus among the samples studied, indicating a potential synergy between an alloy's mechanical strength and its radiation shielding effectiveness. It can be concluded that alloys with higher elastic moduli not only offer better resistance to radiation -induced deformations, enhancing shielding, but also underscore the need for further research on alloys that balance performance, affordability, and environmental impact. The findings underscore the dual importance of composition and mechanical properties in advancing radiological safety and suggest continued investigation into the sustainability and practicality of effective shielding materials.
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    Enhanced radiation shielding via incorporating europium oxide in 316L stainless steel: Synthesis, physical, microstructural, shielding, and mechanical properties
    (Elsevier Editora Ltda, 2025) Tekin, Hüseyin Ozan; Yayla, Nihal; Albayrak, M.Gökhan; Güler, Ömer; Baykal, Duygu Şen; Alkarrani, Hessa; ALMisned, Ghada
    316L stainless steel is widely utilized in various industries due to its excellent corrosion resistance, mechanical strength, and biocompatibility, making it a preferred material for applications in nuclear filed. However, enhancing its radiation shielding and mechanical properties through reinforcement strategies, such as the addition of high-Z materials like Europium(III) oxide, is crucial for extending its functionality in high-radiation environments, where improved performance is essential for safety and durability. In this study, 316L stainless steel composites reinforced with varying amounts of Eu2O3 (1%, 5%, 10%, and 20%) were synthesized and investigated for their structural, mechanical, and radiation shielding properties. X-ray diffraction (XRD) analysis revealed that the face-centered cubic (FCC) structure of the steel matrix was preserved up to 5% Eu2O3 reinforcement, while higher concentrations led to phase formation and crystallographic changes. Scanning electron microscopy (SEM) and energy-dispersive X-ray (EDX) analysis showed uniform element distribution at low reinforcement levels, with particle clustering at 20% Eu2O3. Transmission factors (TFs) were evaluated using PHITS simulations for photon energies of 0.662 MeV, 1.1732 MeV, and 1.3325 MeV. The 20% Eu2O3 composite exhibited the lowest TF and highest attenuation properties, confirmed by mass and linear attenuation coefficients. Elastic modulus values decreased from 224.46 GPa in pure 316L to 189.26 GPa with 20% Eu2O3 reinforcement, reflecting the inverse relationship between mechanical stiffness and radiation shielding performance. Benchmarking against other shielding materials demonstrated superior performance of the Eu2O3-reinforced steel in gamma-ray attenuation. The 20% Eu2O3 composite shows strong potential for applications in nuclear radiation shielding where attenuation efficiency is prioritized over mechanical properties. © 2024 The Authors
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    Examining the trade-off between structural, mechanical properties and shielding performance of Pr2O3-enhanced 316L stainless steel
    (Elsevier ltd, 2025) Yayla, Nihal; Albayrak, M.Gökhan; Güler, Ömer; Baykal, Duygu Şen; Alkarrani, Hessa; Almisned, Ghada; Zakaly, Hesham M.H.; Tekin, Hüseyin Ozan
    This study explores the structural, mechanical, and radiation shielding properties of 316L stainless steel composites reinforced with varying weight percentages of Pr2O3. The aim is to enhance radiation attenuation capabilities while maintaining structural integrity for nuclear applications. The composites were fabricated using the mechanical alloying method, followed by detailed characterization through X-ray diffraction, scanning electron microscopy, and energy-dispersive X-ray spectroscopy. Key radiation shielding parameters, including mass attenuation coefficient, linear attenuation coefficient, half-value layer, and effective atomic number, and transmission factor values were analysed using theoretical and computational models. Additionally, elastic modulus calculations were performed to assess mechanical properties. The results indicate that incorporating Pr2O3 significantly enhances shielding performance. The 316L-SS%20Pr2O3 composite exhibited the highest mass and linear attenuation coefficients values, with a notable reduction in half value layer values compared to the unreinforced 316L stainless steel. At lower photon energies, effective atomic number improved by 39.3 % for the 316L-SS%20Pr2O3 sample, while neutron shielding efficiency also increased. However, the elastic modulus decreased with higher Pr2O3 content, reflecting a trade-off between mechanical stiffness and radiation shielding efficiency. The findings demonstrate that 316L-SS%20Pr2O3 is a promising material for applications requiring superior radiation shielding, particularly in environments where mechanical load is secondary.
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    High-Density Lead Germanate Glasses with Enhanced Gamma and Neutron Shielding Performance: Impact of PbO Concentration on Attenuation Properties
    (Prof.Dr. İskender AKKURT, 2025) Alkarrani, Hessa; Şen Baykal, Duygu; ALMisned, Ghada; Tekin, Hüseyin Ozan
    Lead germanate glasses, improved with lead oxide (PbO), have emerged as effective materials for radiation shielding due to their increased density and structural robustness. The goal of this study is to find out how well lead germanate glasses with PbO concentrations between 20 and 55 mol% can block gamma rays and neutrons. The Phy-X/PSD software was used to obtain important numbers like the mass attenuation coefficient (MAC), the linear attenuation coefficient (LAC), the half-value layer (HVL), the mean free path (MFP), and the fast neutron removal cross section (FNRCS). The results show that the 55PbGe sample, which has the most PbO, has better gamma-ray attenuation and a low energy absorption buildup factor (EABF). This makes it a good choice option for locations requiring compact but efficient radiation shielding. The 50PbGe sample, on the other hand, demonstrates effective neutron shielding capabilities, suggesting it may be suitable for applications requiring protection against both gamma and neutron exposure. Higher PbO content is linked to better radiation blocking, which supports the idea that lead germanate glasses could be used instead of traditional lead-based shielding materials. © IJCESEN.
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    Mechanical and, photon transmission properties of rare earth element (REE) doped BaO-B2O3-Li2O-Al2O3-P2O5 glasses for protection applications
    (Elsevier, 2024) ALMisned, Ghada; Şen Baykal, Duygu; Alkarrani, Hessa; Kılıç, G.; Zakaly, Hesham M. H.; Issa, Shams A. M.; Tekin, Hüseyin Ozan
    This study explores the dual functional capabilities of rare earth (REE) doped BaO-B2O3-Li2O-Al2O3-P2O5 glasses, with an emphasis on the 1.50Dy-Tb-Eu composition, previously recognized for its superior luminescent properties. By employing Monte Carlo simulations and Phy-X/PSD software, we have methodically evaluated the gamma-ray and neutron shielding efficacies of these materials. Our key findings indicate that the 1.50Dy-Tb-Eu sample not only excels in luminescence but also demonstrates superior gamma-ray shielding, characterized by low exposure buildup factors, and other related properties across varying energy spectra. Furthermore, the TbEu3.0 variant, enriched with the highest Europium (Eu) content among the bi-REE doped glasses, exhibited the most effective neutron attenuation. Additionally, our investigation into the mechanical properties of these glasses, through the estimation of their Elastic Moduli using a mixture rule approach, revealed a significant enhancement in stiffness with the incorporation of Dy, Eu, and Tb. The mechanical properties were evaluated using a mixture rule approach to estimate the Elastic Moduli. This highlights the crucial role of these dopants in not only improving the luminescent and radiation shielding capabilities but also in strengthening the mechanical integrity of the glasses. The study substantiates the premise that the integration of specific REE elements significantly enhances the glass materials' shielding properties without compromising their luminescent functionality. The obtained findings would be significant for implications on the development of advanced materials tailored for industries where high optical quality, effective radiation protection, and robust mechanical properties are paramount. It can be concluded that Dy-Tb-Eu incorporation into BaO-B2O3-Li2O-Al2O3-P2O5 glasses can be considered as a monotonic strategy to achieve a harmonious balance between luminescence, radiation shielding, and mechanical performance.
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    Phase Stability, Structural Properties, Electronegativity, Mechanical Properties, and Neutron and Gamma-Ray Attenuation Properties of Cantor High Entropy Alloys for Advanced Nuclear Applications
    (Springer, 2024) Tekin, Hüseyin Ozan; Güler, Ömer; Özkul, İskender; AlMisned, Ghada; Baykal, Duygu Şen; Alkarrani, Hessa; Kılıç, Gökhan
    High Entropy Alloys (HEAs) hold considerable potential for sophisticated nuclear applications, offering a vast spectrum of compositional tuning to enhance mechanical properties at high temperatures, as well as to increase resistance to radiation and corrosion. This study explores the suitability of Cantor HEAs, specifically the CoCrFeMnNi matrix enriched with elements such as Zr, Nb, Mo, Hf, Ta, and W, for nuclear applications. These elements were selected for their high atomic numbers and neutron capture cross-sections, vital for enhancing gamma-ray and neutron shielding properties. Utilizing advanced computational and theoretical methods, the elastic modulus of these alloys was theoretically estimated while their radiation attenuation capabilities were evaluated through different Monte Carlo simulation codes. CoCrFeMnNiW demonstrated the highest elastic modulus (340.9 GPa), indicating significant mechanical robustness. The addition of W resulted in superior gamma-ray attenuation, with the lowest gamma-ray transmission factors and highest neutron shielding effectiveness among the studied alloys. The calculated mass attenuation coefficients and effective removal cross-sections values demonstrate the potential of these HEAs to provide effective radiation shielding. Our results showed a clear correlation between the elastic modulus and radiation attenuation properties, suggesting that mechanical stiffness does not compromise shielding capabilities. The comprehensive analysis of thermodynamic and structural parameters, including entropy of mixing, mixing enthalpy, and Valence Electron Concentration (VEC), provided essential insights into phase stability and microstructural characteristics. It can be concluded that CoCrFeMnNiW and its related Cantor HEAs as promising materials for advancing nuclear technology, offering a new horizon for safer and more efficient nuclear systems. © ASM International 2024.

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