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Öğe Advancing mechanical durability and radiation shielding properties in Silicon dioxide (SiO2) glasses through various incorporations: A comparative analysis(Elsevier B.V., 2024) AlMisned, G.; Sen, Baykal, D.; Alkarrani, H.; Susoy, G.; Tekin, H.O.Silicon dioxide (SiO2) glasses, known for their high thermal stability, excellent optical transparency, and substantial mechanical strength, are crucial in numerous technological applications, including radiation shielding. This research explores the impact of compositional variations in SiO2-based glasses on their mechanical and radiation shielding properties, particularly focusing on the inclusion of heavy metal oxides (HMO) and rare earth elements (REE) like neodymium (Nd). Through the systematic investigation of fifteen distinct glass samples with varying concentrations of specific oxides and elements, we investigate the compositional changes and their influence on physical properties and their effectiveness in attenuating radiation. Our findings demonstrate that the incorporation of Nd significantly enhances the glass's radiation shielding capabilities. Glasses doped with Nd exhibited higher effective atomic numbers and electron densities, which translate to superior attenuation characteristics at lower photon energies. This is highlighted by the exceptional performance of the 20Nd sample, showing the lowest exposure build-up factors (EBF) at 10 mean free paths (mfp), indicating its potential as a premier candidate for shielding applications against various energy levels of radiation. Moreover, the variation in the Elastic Modulus of the glass samples underscores the significant impact of the glass matrix composition on its mechanical properties, suggesting a delicate balance between network formers and modifiers in determining the glass properties. It can be concluded that the neodymium-doped SiO2-based glasses may be considered as targeted compositions in fine-tuning material properties to meet specific application requirements. As the demand for efficient radiation shielding materials grows across medical, industrial, and space exploration sectors, our findings provide a solid foundation for the development of new glass formulations tailored for enhanced mechanical properties and superior radiation protection levels. © 2024 The Author(s)Öğe Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study(Cell Press, 2023) ALMisned, Ghada; Baykal, Duygu Sen; Kilic, G.; Ilik, E.; Rabaa, Elaf; Susoy, G.; Zakaly, Hesham M. H.This study's primary objective is to provide the preliminary findings of novel research on the design of Indium (III) oxide-reinforced glass container that were thoroughly developed for the purpose of a nuclear material container for transportation and waste management applications. The shielding characteristics of an Indium (III) oxide-reinforced glass container with a certain elemental composition against the 60Co radioisotope was thoroughly evaluated. The energy deposition in the air surrounding the designed portable glass containers is measured using MCNPX general-purpose Monte Carlo code. Simulation studies were carried out using LenovoP620 workstation and the number of tracks was defined as 108 in each simulation phase. According to results, the indium oxide-doped C6 (TZI8) container exhibits superior protective properties compared to other conventional container materials such as 0.5Bitumen-0.5 Cement, Pb Glass composite, Steel-Magnetite concrete. In addition to its superiority in terms of nuclear safety, it is proposed that the source's simultaneous observation and monitoring, as well as the C6 (TZI8) glass structure's transparency, be underlined as significant advantages. High-density glasses, which may replace undesirable materials such as concrete and lead, provide several advantages in terms of production ease, non-toxic properties, and resource monitoring. In conclusion, the use of Indium (III) oxide-reinforced glass with its high transparency andÖğe An extensive benchmark analysis of advanced ceramic-concretes towards strategic material selection for nuclear applications and waste management(Elsevier Ltd, 2024) AlMisned, G.; Susoy, G.; Sen, Baykal, D.; Kilic, G.; Tekin, H.O.Ceramic concretes, with their exceptional durability and ability to incorporate a high percentage of heavy metal oxides, are of critical importance for nuclear radiation facilities, offering superior radiation attenuation characteristics essential for long-term safety and protection. This study presents a detailed evaluation of the gamma-ray shielding properties of various concrete composites, including Standard Concrete and Heavy Concretes (HC series), with densities ranging from 1.94 g/cm3 to 4.54 g/cm3. Utilizing computational methods, we analyzed several gamma-ray and neutron shielding parameters such as mass attenuation coefficients, linear attenuation coefficients, half and tenth value layers, mean free paths, exposure build-up factors, effective atomic number (Zeff), effective electron density (Neff), fast neutron effective removal cross-section (?R), and photon transmission factors (TFs). Our research reveals that the shielding efficacy of concrete is intrinsically linked to its density and elemental composition, with higher densities and the incorporation of heavy elements leading to enhanced attenuation capabilities. Among the concretes studied, Limonite with Steel Punch LS-a, which contains 74.53% Fe in its structure, exhibited the lowest transmission factors (TFs) across all tested thicknesses and energy levels (0.662, 1.1732, and 1.3325 MeV), indicating its superior photon attenuation potential. It can be concluded that the concrete samples with a higher Fe (iron) content in their structure demonstrate clear superiority in gamma-ray attenuation properties. © 2024 Elsevier Ltd and Techna Group S.r.l.Öğe Neutron transmission analysis in borated polyethylene, boron carbide, and polyethylene: Insights from MCNP6 simulations(Pergamon-Elsevier Science Ltd, 2024) Almisned, Ghada; Susoy, G.; Tekin, H. O.This study delves into the neutron transmission properties of three pivotal materials: borated polyethylene, boron carbide (B4C), and polyethylene, employing the advanced MCNP6 (version 6.2) Monte Carlo code. The primary objective was to discern the impact of boron content and material density on neutron transmission efficacy. Results highlighted the formidable neutron shielding prowess of B4C, which exhibited the lowest neutron transmission factor among the studied materials. Borated polyethylene samples revealed an inverse correlation between boron concentration and neutron transmission, emphasizing boron's paramountcy in neutron attenuation. In contrast, polyethylene showcased notable neutron moderating capabilities, necessitating synergistic integration with materials possessing higher neutron absorption cross-sections for superior neutron shielding. Material density and the presence of other elemental constituents further influenced neutron transmission. The research provides a comprehensive understanding of neutron-material interactions, setting the groundwork for enhanced safety measures in nuclear applications.Öğe The role of Ag2O incorporation in nuclear radiation shielding behaviors of the Li2O-Pb3O4-SiO2glass system: A multi-step characterization study(De Gruyter Open Ltd, 2023) Almisned, G.; Susoy, G.; Zakaly, H.M.H.; Rabaa, E.; Kilic, G.; Ilik, E.; Sen Baykal D.We report the gamma-ray shielding properties of five different lithium silicate glasses based on the (40 - x) Li2O-10Pb3O4-50SiO2 nominal composition. Transmission factor values and some basic shielding parameters such as linear (?) and mass attenuation coefficients (?/?), half-value layer, tenth value layer, and mean free path (MFP) values of the investigated glass samples are determined in a large photon energy range. Using the G-P fitting method at various MFP values, the exposure buildup factor and energy absorption buildup factor values of the examined glasses are also calculated. Based on the findings, it can be concluded that the S5 glass specimen, which exhibits the greatest Ag2O additive and density among the various glass samples, represents a favorable choice for the purpose of shielding against gamma radiation. © 2023 the author(s), published by De Gruyter.
