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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 Ozan
We 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.
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 Ozan
Doping 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.
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 Ozan
The 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.
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 Ozan
No Abstract Available.
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, Antoaneta
Thallium-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.
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 Ozan
We 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.
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 Ozan
We 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.
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 Ozan
The 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.
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.
A comprehensive evaluation of the attenuation characteristics of some sliding bearing alloys under 0.015–15 meV gamma-ray exposure
(MDPI, 2022) Algethami, Merfat; Ibraheem, Awad A.; Issa, Shams A. M.; Tekin, Hüseyin Ozan; Ene, Antoaneta; Pyshkina, Maria; Rashad, Mohamed; Almisned, Ghada; Zakaly, Hesham M. H.
In this study, three different sliding bearing alloy samples were investigated in terms of their performance on attenuation characteristics and behavioral attitudes under 0.015–15 MeV gamma-ray exposure. Accordingly, different types of advanced calculation methods were utilized to calculate the radiation shielding parameters. Next, several gamma-ray shielding parameters and exposure rates in addition to fast neutron removal cross-section were determined. Furthermore, exposure and energy absorption buildup factors were determined by using G-P fitting method. Mass attenuation coefficients (MAC) values were recorded as 2.5246, 2.5703, and 2.5827 (cm2 /g) for Alloy1, Alloy2, and Alloy3 samples at 15 MeV photon energy, respectively. At 40 mfp, the highest EBF values were reported as 1,376,274, 1,003,593, and 969,373 for Alloy1, Alloy2, and Alloy3 samples. The results of this extended investigation showed that the Alloy3 sample with the highest Pb reinforcement amount has superior shielding capability among the investigated samples. It can be concluded from the results that substitution of Pb with Bi in the recent alloy structure has a monotonic effect on different types of shielding parameters. Therefore, it can also be concluded that Pb is a remarkable tool for the improvement of the shielding properties of studied alloy structures. © 2022 by the authors. Licensee MDPI, Basel, Switzerland.
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 GmbH
A comprehensive microstructural and transmission analysis on oxide dispersion-strengthened (ODS) alloys: Impact of erbium oxide (Er2O3) concentration on physical, structural, gamma-ray, and neutron attenuation properties
(Elsevier Sci Ltd, 2024) Gunoglu, Kadir; Guler, Seval Hale; Guler, Omer; Almisned, Ghada; Ozkavak, Hatice Varol; Albayrak, M. Gokhan; Akkurt, Iskender
This study explores the impact of integrating varying concentrations of Erbium Oxide (Er2O3) into Oxide Dispersion Strengthened (ODS) alloys, specifically focusing on gamma-ray and neutron attenuation properties. Utilizing a 316L stainless steel matrix, Er2O3 was methodically incorporated in concentrations ranging from 1 % to 21 % by weight. The structural and radiation attenuation properties of the resultant alloys were comprehensively analyzed using techniques such as X-ray diffraction (XRD), Scanning Electron Microscopy (SEM), and experimental gamma-ray transmission studies. The results demonstrate a significant enhancement in gamma-ray shielding with increased Er2O3 content. This enhancement is quantitatively evidenced by increased linear attenuation coefficient, elevated effective Electron Density (Neff), reduced Half-Value Layers (HVL), and higher effective atomic numbers (Zeff). These findings are crucial for nuclear applications where efficient gamma-ray shielding is paramount. Conversely, a decrease in the effective removal cross section (sigma R) for neutron attenuation was observed with higher Er2O3 concentrations. This suggests a potential compromise in neutron shielding efficiency, attributed to the dilution of neutron-absorbing base elements in the alloy. Additionally, the study reveals notable changes in the microstructural properties of the alloys, including alterations in particle size, distribution, and agglomeration, influenced by varying Er2O3 concentrations. In conclusion, this research provides valuable insights into the design of ODS alloys for nuclear radiation shielding, highlighting the balance between gamma-ray attenuation and neutron shielding properties. The study's findings contribute to the development of advanced materials for safer and more efficient nuclear technology applications.
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; Şen Baykal, Duygu; Kılıç, Gökhan; İlik, Erkan; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan
We examine the nuclear safety properties of a newly designed cadmiumoxide-rich glass container for nuclear material to a bitumen-reinforced concrete container. Individual transmission factors, detectormodelling, 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 dioxiderich 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.
Determination of gamma-ray transmission factors of WO3-TeO2-B2O3 glasses using MCNPX monte carlo code for shielding and protection purposes
(DE GRUYTER POLAND SP Z O O, 2022) Almisned, Ghada; Susoy, Gülfem; Kılıç, Gökhan; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan; Baykal, Duygu Şen
The aim of this study is to assess the individual gamma-ray transmission factors (TFs) and some fundamental gamma-ray attenuation properties of several types of glasses based on WO3-TeO2-B2O3 glasses system. MCNPX (version 2.7.0) is used for the calculation of TFs. Other critical parameters are determined using the Phy-X/PSD program. To determine the TFs of studied glasses, several medical radioisotopes are determined along with their characteristic gamma-ray energies. The superior values for the investigated parameters are found in glass sample S6. Furthermore, the exposure build-up factor and energy absorption build-up factor values for glass sample S6 were the lowest. S6 glass sample with the chemical composition 0.03833B + 0.26075O + 0.11591Zn + 0.52783Te + 0.05718W and a density of 3.3579 g/cm(3) is found to have exceptional gamma-ray attenuation qualities, according to our findings. It can be concluded that the prospective attributes of WO3-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.
Diagnostic and therapeutic radioisotopes in nuclear medicine: Determination of gamma-ray transmission factors and safety competencies of high-dense and transparent glassy shields
(DE GRUYTER POLAND SP Z O O, 2022) Erdemir, Rabiye Uslu; Kılıç, Gökhan; Baykal, Duygu Şen; Almisned, Ghada; Issa, Shams A. M.; Zakaly, Hesham M. H.; Ene, Antoaneta; Tekin, Hüseyin Ozan
We present the findings of an extensive examination on newly designed CdO-rich and transparent glass shields for nuclear medicine facilities in lieu of traditional and unfavorable materials, such as lead and concrete. Gamma-ray transmission factors of newly designed glass shields are determined using a variety of diagnostic, therapeutic, and research radioisotopes, including Ga-67, Co-57, In-111, Tl-201, Tc-99m, Cr-51, I-131, Co-58, Cs-137, Ba-133, and Co-60. A general-purpose Monte Carlo code MCNPX (version 2.7.0) is used to determine the attenuation parameters of different material thicknesses. Next, the findings are compared using a standard concrete shielding material. The results indicate that adding more CdO to the glass composition improves the overall gamma-ray attenuation properties. As a result, among the heavy and transparent glasses developed, the C40 sample containing 40% CdO exhibited the best gamma-ray absorption properties against all radioisotopes. Furthermore, the gamma-ray absorption characteristics of this created high-density glass were shown to be better to those of a standard and heavy concrete sample. It can be concluded that the newly developed CdO-rich and transparent glass sample may be used in medical radiation fields where the radioisotopes examined are used in daily clinical and research applications.
The effect of Annona muricata (Graviola) on the prevention of brain damage due to ionizing radiation in rats
(Cell Press, 2024) Elmas, Ozlem; Keskin, Emrah; Sahin, Havva Hande Keser; Guven, Berrak; Almisned, Ghada; Zakaly, Hesham M. H.; Tekin, H. O.
In this study, it was aimed to evaluate the effect of ethanol extract of Annona Muricata (AM) leaves in the prevention of brain damage caused by ionizing radiation (IR). This study was conducted in the Experimental Animal Research Unit of a university with 28 adults female Wistar Albino rats. The experimental groups were as follows: Control group (n = 8), AM group (n = 6), IR group (n = 8), AM + IR group (n = 6). In the IR group, astrocyte hypertrophy, microglial reaction and inflammatory reaction levels were significantly higher than the control and AM groups (P < 0.001). Edema was significantly higher in the IR group compared to the control group (P=0.001). The MDA of the IR group was significantly higher compared to the control group and AM group (P=0.031, P=0.006, respectively). The MDA of the AM + IR group was significantly higher than the AM group (P=0.039). Our findings show that histomorphology and oxidant damage caused by IR can be ameliorated using AM, as demonstrated by the comparison of the controls to AM + IR recipients, which showed similar histomorphology and oxidant damage levels.
Elucidating the influences of tantalum (V) oxide in Bi2O3–TeO2–ZnO ternary glasses: an experimental characterization study on optical and nuclear radiation transmission properties of high-density glasses
(Elsevier, 2022) İlik, Buse Özen; Kılıç, Gökhan; İlik, Erkan; Kavaz, Esra; Almisned, Ghada; Tekin, Hüseyin Ozan
We report the optical and experimental gamma-ray and neutron attenuation properties of tantalum pentoxide reinforced Bi2O3–TeO2–ZnO ternary glasses with a nominal composition of 10Bi2O3–70TeO2-(20-x)ZnO-xTa2O5 (where x = 0,2,4, and 6 mol%). Measurements of transmittance and absorbance spectra for all of the synthesized samples are performed with Analytik Jena Specord 210 plus device between the range of 190–1100 nm. Moreover, 133Ba and 241Am/Be sources are utilized for experimental gamma-ray and neutron attenuation studies of BTZT glasses. According to results, the absorption edge is consistently moved from 380 nm to 390 nm as a result of ZnO/Ta2O5 translocation. In addition to decrease in optical band gap values of glass series, the fact that doping the structure containing Ta2O5 is lead to an increase in Urbach energies. The obtained irregularity through an increasing Ta2O5 additive is also changed the overall nuclear radiation attenuation properties of the BTZT glasses. The gamma-ray attenuation properties are obviously enhanced within the energy range of 133Ba radioisotope. The attenuation properties against fast neutron emitted from 241Am/Be were significantly enhanced through increasing Ta2O5 contribution. It can be concluded that BTZT6 glass sample may be regarded as a beneficial glass composition for multifunctional applications. It can be also concluded that ZnO/Ta2O5 translocation in Bi2O3–TeO2–ZnO ternary glasses may be regarded as a monotonic tool where the neutron attenuation properties should be strengthened in addition to gamma attenuation properties.
Energy deposition responses, transmission factors, and radiation interaction properties of some antibiotics: A critical assessment for substantial molecular alterations as a function of radiation exposure
(Pergamon-Elsevier Science Ltd, 2024) Almansoori, Asma; Almisned, Ghada; Sen Baykal, Duygu; Kilic, Ceyda Sibel; Tekin, H. O.
This study addresses the underexplored area of radiation interaction properties of antibiotics and their implications for stability, efficacy, and structural integrity. Focusing on a range of antibiotics classified by the United Arab Emirates National AMR Surveillance system, the research evaluates key metrics such as attenuation coefficients, effective electron density, exposure buildup factor, and photon transmission factors. Utilizing advanced MCNPX Monte Carlo simulation, we observed varied interaction patterns among different antibiotics, with significant findings on their photon interaction characteristics. The study highlights the potential molecular changes in antibiotics due to radiation exposure, emphasizing the importance of such research in fields from medical radiography to space exploration. Results indicate that radiation exposure can significantly affect antibiotic properties, underscoring the need for careful evaluation of drugs in radiation-rich environments to ensure their effectiveness and safety.
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.
Exploring critical behavioral differences in physical, structural, and nuclear radiation attenuation properties of produced High Entropy Alloy (HEA) and Refractory-High Entropy Alloy (RHEA) samples
(Elsevier, 2024) Guler, Seval Hale; Guler, Omer; Kavaz, E.; Almisned, Ghada; Issa, Bashar; Tekin, H. O.
Refractory-High entropy alloys (RHEAs) are known for their exceptional mechanical and radiation-resistant properties, making them promising materials for use in nuclear reactors. Their high entropy composition, which consists of multiple elements in roughly equal proportions, can create a stable microstructure that withstands high levels of radiation damage. The objective of this work is to further our comprehension of the unique behavioral, physical, structural, and nuclear radiation attenuation characteristics shown by High-Entropy Alloys (HEA) and Refractory-High entropy alloy (RHEA) materials. Accordingly, two high entropy alloy (HEA) samples through two different compositions were produced. The first composition under consideration is the typical high-entropy alloy (HEA) defined as MnCrFeNiCoMo0.5. The second composition under consideration is a refractory high entropy alloy (RHEA) characterized by the following elemental composition: TiZrNbHfVTa0.1. SEM and EDX analyses were conducted in terms of determining their physical and structural attributes. Next, a133Ba radioisotope together with a HPGe detector were utilized for gamma-ray transmission experiments. Finally, a241Am/Be source and a gas proportional detector were used for neutron absorption experiments for HEA and RHEA samples. The alloy structures displayed a unique degree of uniformity. Throughout the RHEA phase, the incorporation of refractory elements did not provide any discernible adverse impacts on the physical stability. The counting spectrum provided a clear explanation of the gamma ray absorption features shown by the RHEA (R) sample, highlighting its exceptional absorption properties. Regarding the absorption properties of neutrons, it was observed that RHEA had a comparatively reduced amount of absorption. Therefore, it can be concluded that the basic structure of RHEA grants it superior gamma-ray attenuation qualities compared to HEA. It can be concluded that RHEA demonstrates superior applicability as a material in comparison to HEA, especially in situations involving the use of fuel rods, where maintaining of neutron quantity has paramount importance for achieving optimum neutron activation.

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