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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 Designing a Lead-free and high-density glass for radiation facilities: Synthesis, physical, optical, structural, and experimental gamma-ray transmission properties of newly designed barium-borosilicate glass sample(Elsevier Science Sa, 2023) Sen Baykal, Duygu; Kilic, G.; Ilik, Erkan; Kavaz, E.; ALMisned, Ghada; Cakirli, R. B.; Tekin, H. O.We report the design, synthesis, optical, structural, and gamma-ray attenuation properties of a newly developed Lead-free and high-density borosilicate glass sample for its potential applications in medical and industrial ra-diation facilities. A barium-borosilicate glass sample (BSBaZn) was designed and synthesized using nominal composition of 7B2O3-50SiO2-38ZnO-5BaO. The FTIR spectrum of the BSBaZn is revealed four fundamental regions. These regions are 400-620 cm-1, 620-770 cm-1, 800-1210 cm-1, and 1210-1500 cm-1. Transmittance rate in the wavelength range of 350-1100 nm is reported as 80 %. A high-purity Germanium (HPGe) detector along with an energetic 133Ba radioisotope is also utilized for experimental gamma-ray transmission studies. Various fundamental gamma-ray shielding parameters of BSBaZn are determined and accordingly compared with many other glass shields. MCNPX (version 2.7.0) general purpose Monte Carlo code is utilized for gamma-ray transmission factor (TF) values. The results showed that the synthesized BSBaZn sample has promising struc-tural, optical, and physical properties in addition to promising gamma-ray attenuation properties. The high transparency of BSBaZn along with its high-density may be considered as an important selection criterion for its implementation in protection purposes in medical and industrial radiation facilities, where the source and pa-tients monitoring play a significant role.Öğe Enhancing mechanical, physical, radiation attenuation properties in alumino-barium-titanium-calcium-lithium glasses for nuclear applications: The pivotal role of TiO2 additives(Pergamon-Elsevier Science Ltd, 2024) Sen Baykal, Duygu; Afaneh, F.; Susoy, Gulfem; Al-Omari, S.; Almisned, Ghada; Kilic, G.; Khattari, Z. Y.This study focused on enhancing key material properties of Alumino-Barium-Titanium-Calcium-Lithium glasses for nuclear applications, specifically by integrating increasing amounts of TiO2 additives. Utilizing the MCNPX general-purpose Monte Carlo code, version 2.7.0, the research aimed to ascertain Transmission Factor (TF) values across a spectrum of well-known radioisotope energies. This analysis was conducted for glass samples with varying thicknesses, ranging from 0.5 cm to 3 cm. The study also delved into the gamma-ray shielding characteristics of these glasses at energy levels between 0.015 and 15 MeV, uncovering notable findings. In exploring the T1 to T12 glass system, various physical and optical methods were employed to measure key parameters like glass density (rho glass), molar volume (Vm), oxygen molar volume (OMV), and oxygen packing density (OPD). A significant outcome of this research was the observation that with an increase in TiO2 content, there was a corresponding rise in glass density, from 3.727 g/cm3 to 3.825 g/cm3. Furthermore, the study noted alterations in the physical and mechanical properties of the glasses. Most notably, the T12 glass sample, which contained the highest concentration of TiO2, exhibited superior gamma-ray shielding properties compared to the other glass compositions analysed.Öğe 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 An investigation on protection properties of Tantalum (V) oxide reinforced glass screens on unexposed breast tissue for mammography examinations(Elsevier Sci Ltd, 2024) Alan, H. Y.; Almisned, G.; Yilmaz, A.; Susam, L. A.; Ilik, E.; Kilic, G.; Ozturk, G.Introduction: The utilization of radiation shielding material positioned between the both breasts are crucial for the reduction of glandular dose and the safeguarding of the contralateral breast during mammographic procedures. This study proposes an alternative substance for shielding the contralateral breast from radiation exposure during mammography screening.Methods: In this study, we present an analysis of the shielding effectiveness of transparent glass that has been doped with Tantalum (V) oxide encoded as BTZT6. The evaluation of this shielding material was conducted using the MCNPX code, specifically for the ipsilateral and contralateral breasts. The design of the left and right breast phantoms involved the creation of three-layer heterogeneous breast phantoms, consisting of varying proportions of glandular tissue (25%, 50%, and 75%). The design of BTZT6 and lead-acrylic shielding screens is implemented using the MCNPX code. The comparative analysis of dose outcomes is conducted to assess the protective efficacy of BTZT6 and lead-acrylic shielding screens.Results: The utilization of BTZT6 shielding material resulted in a reduction in both breast dose and skin dose exposure when compared to the lead-acrylic shield. Conclusion: Based on the findings acquired, the utilization of BTZT6 shielding material screens during mammography procedures involving X-rays with energy levels ranging from 26 to 30 keV is associated with a decrease in radiation dose.Implications for practice: It can be inferred that the utilization of BTZT6 demonstrates potential efficacy in mitigating excessive radiation exposure to the breasts and facilitating the quantification of glandular doses in mammography procedures.(c) 2023 The College of Radiographers. Published by Elsevier Ltd. All rights reserved.Öğe KERMA, projected range, mass stopping power and gamma-ray shielding properties of antimony and tellurium reinforced iron phosphate glasses(Elsevier Ltd, 2024) Alan, H.Y.; Yilmaz, A.; Susam, L.A.; Ozturk, G.; Kilic, G.; Ilik, E.; Oktik S.In this study, the radiation shielding effectiveness of iron phosphate glass (Fe2O3–P2O5) doped with antimony (Sb) and tellurium (Te) is assessed in detail using advanced computational methods. The projected range, mass stopping power, and KERMA (Kinetic Energy Released per unit MAss) for fourteen different iron phosphate glass samples are calculated through the PAGEX and SRIM software. Mass attenuation coefficients, linear attenuation coefficients, mean free path, half value layers, tenth value layers, and effective atomic number are determined in 0.015–15 MeV energy range. The research reveals that doping iron phosphate glass with Sb2O3 significantly enhances its shielding capabilities when compared to the inclusion of TeO2. Another important aspect is, the IPGSb50 sample exhibited the highest KERMA values, indicating its exceptional capacity for energy absorption from ionizing radiation. Additionally, the IPGSb50 sample exhibited the lowest projected range for alpha particles, also this sample demonstrated a similar prowess in limiting the penetration of proton particles. Our findings indicate that the incorporation of Sb2O3 and TeO2 into iron phosphate glass matrices results in a noticeable improvement in gamma radiation shielding effectiveness. These doped glasses could serve as potent alternatives to traditional lead-based shielding materials, offering a safer and potentially more effective barrier against a variety of radiation types. © 2024 Elsevier LtdÖğe Mechanical properties, elastic moduli, and gamma ray attenuation competencies of some TeO2-WO3-GdF3glasses: Tailoring WO3-GdF3substitution toward optimum behavioral state range(De Gruyter Open Ltd, 2023) Almisned, G.; Rabaa, E.; Sen, Baykal, D.; Kavaz, E.; Ilik, E.; Kilic, G.; Zakaly H.M.H.We report the mechanical properties, elastic moduli, and gamma ray attenuation properties of some TeO2-WO3-GdF3 glasses. Using the chemical composition of the selected glasses, the dissociation energy per unit volume (G t ) and the packing density (V t ) were calculated. Using the G t and V t values, Young's, Shear, Bulk, Longitudinal Modulus, and Poisson's ratio of the glasses are calculated. Next several fundamental gamma ray attenuation properties such as linear and mass attenuation coefficients, half value layer, mean free path, effective atomic number, effective electron density, effective conductivity, exposure, and energy absorption buildup factors are calculated in 0.015-15 MeV energy range. As a consequence of WO3-GdF3 substitution, the glass densities are observed in different values. The overall gamma ray attenuation properties are found to be enhanced through WO3 addition. Moreover, the increasing WO3 incorporation into glass configuration decreases the overall elastic moduli of glasses. It can be concluded that increasing WO3 may be a useful tool for enhancing the gamma ray attenuation qualities and decreasing the elastic moduli of TeO2-WO3-GdF3 in situations where a material with versatile mechanical properties is required. © 2023 the author(s), published by De Gruyter.Öğe Mechanical, gamma rays and neutron radiation transmission properties for some ZnO-TeO2-P2O5-ZnX glasses(Elsevier Sci Ltd, 2023) Kilic, G.; Ilik, E.; Kavaz, E.; Almisned, Ghada; Sen Baykal, Duygu; Tekin, H. O.Oxyhalide glasses are utilized in the process of immobilizing nuclear waste and function as scintillating agents for the purpose of radiation detection. The objective of this study is to examine the enhanced mechanical and radiation attenuation characteristics of newly developed oxyhalide glasses by incorporating zinc-iodide. This study investigates the synthesis process, mechanical properties, and experimental gamma-neutron radiation transmission properties. A halogen-free base glass, consisting of an oxide mixture of P2O5, TeO2, and ZnO, was synthesized. Following that, the initial glass composition was further strengthened by the addition of zinc bromide (ZnBr2), zinc chloride (ZnCl2), zinc fluoride (ZnF2), and zinc iodide (ZnI2) in a successive manner. The experimental configuration entailed positioning circular glass samples between a 133Ba radioisotope and a Canberra High Purity Germanium (HPGe) detector. The determination of attenuation coefficients is achieved through the measurement of individual attenuation properties. Afterwards, theoretical approaches are utilized to determine the mechanical characteristics of halogenated glasses, including Young's modulus (Y), Bulk modulus (K), Shear modulus (G), Longitudinal modulus (L), and Poisson's modulus (v). The results of the study suggest that the implementation of the halogenation process on the P2O5-TeO2-ZnO base composition led to a significant enhancement in the examined properties. The incorporation of zinc-iodide in the halogenation process resulted in a significant improvement in the gamma absorption properties. The utilization of zinc in the halogenation process demonstrates multifunctional capabilities, which involve the potential to enhance various glass properties, including durability and gamma-ray absorption properties. It can be concluded that zinc-iodide demonstrates enhanced halogenation capabilities in comparison to zinc bromide, zinc chloride, and zinc fluoride.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.Öğe The role of ZrO2 as glass-network former on radiation transmission properties of aluminoborosilicate (ABS) glasses: A glass type for nuclear waste immobilization(Elsevier Sci Ltd, 2023) Almisned, Ghada; Sen Baykal, Duygu; Ilik, E.; Kilic, G.; Tekin, H. O.We report the gamma-ray shielding properties, transmission factors and, effective removal cross section values of several aluminoborosilicate glasses that have been synthesized through various glass-forming materials such as Al2O3, B2O3, SiO2, and ZrO2. The study utilized the elemental compositions and densities of eight different glass samples as input variables in theoretical calculations and Monte Carlo simulations. According to the results obtained, it was seen that the network-forming type used in aluminoborosilicate glasses had a direct effect on the radiation absorption properties of the glasses. The utilization of ZrO2 and Cs2O at the highest concentration as the network former and glass network modifier in the NCBZ-6 sample yielded the most advantageous results in relation to its gamma-ray absorption capabilities. The benefit is intrinsically related to the heightened density of glass and the incorporation of compounds with increased atomic numbers, both of which are fundamental characteristics desired in materials designed for the purpose of gamma-ray absorption. However, the enhanced capability of ZrO2 to absorb gamma-rays excludes the absorption of high-energy neutrons. The absence of boron trioxide (B2O3) in the NCBZ-6 sample can be ascribed to its restricted availability against fast neutrons. The continued existence of ZrO2 as a network forming in the investigated ABS glasses is likely to result in improved material homogeneity and progressive enhancement of gamma-ray absorption characteristics. It can be concluded that the incorporation of ZrO2 as a network-former component may be an appropriate strategy to enhance the gamma-ray shielding capabilities of aluminoborosilicate glasses.Öğe Tailoring a correlation between fracture resistance improvement, elastic moduli, mechanical and nuclear radiation shielding properties for sodium-borate glasses through Gallium(III) oxide incorporation(Elsevier, 2023) Almisned, Ghada; Khattari, Z. Y.; Sen Baykal, Duygu; Susoy, Gulfem; Kilic, G.; Ene, Antoaneta; Tekin, H. O.In the event of unanticipated events or emergency situations, such as equipment malfunctions or accidents, it is crucial for radiation shielding materials to preserve their structural integrity. Enhancing the fracture resistance of glasses has a wide range of benefits that extend to safety, durability, cost savings, energy efficiency, environmental considerations, technological innovation, consumer confidence, manufacturing efficiency, and reduced downtime. This research examines the characteristics of sodium-borate glasses with a nominal composition of 25Na2O-xGa2O3-(75-x)B2O3, (where x: 5, 10, 15, 20, 25, 27.5, and 30 mol%). The aim is to enhance fracture resistant qualities and radiation absorption with the addition of Ga2O3 into the glass composition. In addition to elastic moduli and mechanical properties, gamma-ray and fast neutron removal cross section values are determined for each glass sample. In addition to enhancing mechanical characteristics and elastic moduli, the use of Ga2O3 reinforcement has shown notable improvements in the gamma-ray and fast neutron absorption properties of sodium-borate glass samples. The NGB31.4 sample demonstrated the highest level of improvement in gammaray and neutron absorption characteristics. For example, the mass attenuation coefficients were calculated as 1.86645 cm2/g, 1.92189 cm2/g, 1.98875 cm2/g, 2.04052 cm2/g, 2.10506 cm2/g, 2.16271 cm2/g, and 2.17266 cm2/g for NGB5, NGB10, NGB15, NGB20, NGB25, NGB30.5, and NGB31.4 at 15 MeV photon energy, respectively. This enhancement was accomplished by incorporating Ga2O3 into the baseline sample at a mole percentage of 31.4 %. Hence, it can be concluded that the incorporation of Ga2O3 into sodium-borate glasses has the potential to serve as a systematic mechanism, leading to enhancements in mechanical strength and radiation absorption characteristics, thereby making these glasses more suitable for their intended applications. Among these samples, the greatest level of integration observed was 31.4 % mole Ga2O3. The lack of ability to examine the behavioral alterations resulting from higher Ga2O3 content in sodium-borate glasses may be regarded as a limitation of the present study. However, it is very advisable to do more research among the scientific community to thoroughly explore the potential impact of Ga2O3 on sodium-borate glasses.Öğe Titanium alloys: A closer-look at mechanical, gamma-ray, neutron, and transmission properties of different grade alloys through MCNPcode application(Korean Nuclear Society, 2024) ALMisned, G.; Guler, O.; Sen, Baykal, D.; Kilic, G.; Tekin, H.O.Titanium alloys play a vital role in optimizing the effectiveness and security of nuclear reactors, strengthening structural durability, and facilitating the effective handling of nuclear waste. The aim of this study is to investigate the gamma-ray, neutron, and transmission properties of four common titanium alloys through the examination of the deposited energy amount in the liquid sodium coolant material, in relation to the mechanical properties of these alloys. MCNP (version 6.3) is utilized for designing the titanium pipes. Next, the pipes were re-designed considering the elemental mass fractions and densities of the investigated titanium alloys. Grade 26 sample is reported with the highest values of mass attenuation coefficients and the lowest HVL values among those investigated alloys. Grade 26 is reported to have the lowest TF value, whereas Grade 12 demonstrated the highest TF value. The highest Effective Removal Cross Section (?R, 1/cm) value against fast neutrons is reported for Grade 26. The utilization of Grade 26 sample as pipe material resulted in the lowest deposited energy amount (MeV/g) and subsequent lowest contamination in the coolant material. Out of the alloys that were chosen for analysis, it has been determined that Grade 26 exhibits the highest level of strength. It can be concluded that the Grade 26 alloy exhibits desirable characteristics for applications in nuclear technologies that require superior gamma-ray and neutron absorption properties, as well as exceptional mechanical properties. Nevertheless, it is essential to emphasize the importance for ongoing studies to enhance the existing material properties of Grade 26, with the aim of achieving improved safety and efficacy in nuclear applications. © 2024 Korean Nuclear SocietyÖğe Toward the strengthening of radioprotection during mammography examinations through transparent glass screens: A benchmarking between experimental and Monte Carlo simulation studies(Frontiers Media Sa, 2023) ALMisned, Ghada; Elshami, Wiam; Rabaa, Elaf; Kilic, G.; Ilik, E.; Sen Baykal, Duygu; Ene, AntoanetaIntroductionA lead-acrylic protective screen is suggested to reduce radiation exposure to the unexposed breast during mammography. The presence of toxic lead in its structure may harm the tissues with which it comes in contact. This study aimed to design a CdO-rich quaternary tellurite glass screen (C40) and evaluate its efficiency compared to the Lead-Acrylic protective screen. MethodsA three-layer advanced heterogeneous breast phantom designed in MCNPX (version 2.7.0) general-purpose Monte Carlo code. Lead acrylic and C40 shielding screens were modeled in the MCNPX and installed between the right and left breast. The reliability of the absorption differences between the lead acrylic and C40 glass were assessed. Results and discussionThe results showed that C40 protective glass screen has much superior protection properties compared to the lead acrylic protective screen. The amount of total dose absorbed in the unexposed breast for C40 was found to be much less than that for lead-based acrylic. The protection provided by the C40 glass screen is 35-38% superior to that of the Lead-Acrylic screen. The C40 offer the opportunity to avoid the toxic Pb in the structure of Lead-Acrylic material and may be utilized for mammography to offer superior radioprotection to Lead-Acrylic and significantly lower the dose amount in the unexposed breast. It can be concluded that transparent glass screens may be utilized for radiation protection purposes in critical diagnostic radiology applications through mammography.Öğe Tungsten (VI) oxide reinforced antimony glasses for radiation safety applications: A throughout investigation for determination of radiation shielding properties and transmission factors(Cell Press, 2023) AlMisned, Ghada; Sen Baykal, Duygu; Ilik, Erkan; Abuzaid, Mohammed; Issa, Shams A. M.; Kilic, G.; Zakaly, Hesham M. H.We report the functional assessment of tungsten (VI) oxide on gamma-ray attenuation properties of 60Sb2O3-(40-x)NaPO3-xWO3 antimony glasses. The elemental mass-fractions and glass densities of each glass sample are specified separately for the MCNPX Monte Carlo code. In addition to fundamental gamma absorption properties, Transmission Factors throughout a broad radioisotope energy range were measured. According to findings, holmium (Ho) incorporation into the glass structure resulted in a net increase of 0.3406 g/cm3, whereas cerium (Ce) addition resulted in a net increase of 0.2047 g/cm3. The 40% WO3 reinforced S7 sample was found to have the greatest LAC value, even though seven glass samples exhibited identical behavior. The S2 sample had the lowest HVL values among the glass groups evaluated in this work, computed in the energy range of 0.015-15 MeV. The lowest EBF and EABF values were reported for 40% WO3 reinforced S7 sample with the highest LAC and density values. According to the findings of this research, WO3 will likely make a significant contribution to the gamma ray absorption properties of antimony glasses, which are employed for optical and structural modification. Therefore, it can be concluded that WO3 may be treated monotonically and can be employed successfully in circumstances where gamma-ray absorption characteristics, optical properties, and structural qualities need to be enhanced.Öğe Utilization of three-layers heterogeneous mammographic phantom through MCNPX code for breast and chest radiation dose levels at different diagnostic X-ray energies: A Monte Carlo simulation study(Frontiers Media Sa, 2023) ALMisned, Ghada; Elshami, Wiam; Kilic, G.; Rabaa, Elaf; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, H. O.IntroductionWe report the breast and chest radiation dose assessment for mammographic examinations using a three-layer heterogeneous breast phantom through the MCNPX Monte Carlo code. MethodsA three-layer heterogeneous phantom along with compression plates and X-ray source are modeled. The validation of the simulation code is obtained using the data of AAPM TG-195 report. Deposited energy amount as a function of increasing source energy is calculated over a wide energy range. The behavioral changes in X-ray absorption as well as transmission are examined using the F6 Tally Mesh extension of MCNPX code. Moreover, deposited energy amount is calculated for modeled body phantom in the same energy range. Results and discussionsThe diverse distribution of glands has a significant impact on the quantity of energy received by the various breast layers. In layers with a low glandular ratio, low-energy primary X-ray penetrability is highest. In response to an increase in energy, the absorption in layers with a low glandular ratio decreased. This results in the X-rays releasing their energy in the bottom layers. Additionally, the increase in energy increases the quantity of energy absorbed by the tissues around the breast.
