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Öğe A comprehensive study on structural properties, photon and particle attenuation competence of CoNiFeCr-Ti/Al high entropy alloys (HEAs)(Elsevier Science Sa, 2023) Sakar, Erdem; Guler, Omer; Alim, Buenyamin; Say, Yakup; Dikici, BurakIt is well known that high entropy alloys (HEAs) have a wide range of potential applications as radiation shielding due to their superior properties. The CoNiFeCr-Ti/Al compositions were chosen for their low cost as HEA in this study. The HEAs were successfully produced using the mechanical alloying (MA) method with equimolar CoNiFeCr, CoNiFeCrAl, and CoNiFeCrTi compositions. The production and structural properties of the alloys were investigated in detail. Besides, the photon and particle radiation shielding properties of the HEAs were calculated with the help of Phy-X/PSD, SRIM (10 keV-20 MeV), and ESTAR (10 keV-20 MeV) programs. The photon-matter interaction parameters were calculated in both specific photon energies emitted from 241Am, 133Ba, 109Cd, 60Co, 137Cs, 131I, and 22Na nuclides and a continuous energy range of 15 keV-15 MeV. The characterization of the alloys was investigated by using X-ray diffraction (XRD) and scanning electron microscopes (SEM) attached to an energy dispersive spectroscopy (EDX). It was found that the HEAs have a highly amorphous structure due to the selected production method. The crystal size of the alloys was calculated as 70, 35, and 20 nm for CoNiFeCr, CoNiFeCrAl, and CoNiFeCrTi, respectively. In terms of shielding properties, it has been determined that the produced HEAs have better shielding char-acteristics for photon and particle radiations than standard shielding concretes. In addition, the results demonstrated that CoNiFeCr alloy, which has the best shielding ability among the HEA alloys, can be used as a shielding material application requiring photon, electron, proton, alpha, and neutron radiations. (c) 2022 Elsevier B.V. All rights reserved.Öğe Determination of the molecular structure and spectroscopic properties of capsaicin(Pergamon-Elsevier Science Ltd, 2023) Cinar, Mehmet; Alum, Bunyamin; Alum, Zuhal; Sakar, ErdemIn this study, the ground state molecular structure and spectroscopic features of cis-and trans-forms of capsaicin were investigated using DFT (B3LYP) invoking 6-311++G(d,p) basis set. The optimized geometry of capsaicin was determined for the isolated molecule in a vacuum, and then the vibrational spectra -IR and Raman-were obtained, and the assignments of fundamental vibrational modes were done. By applying the GIAO method, proton and carbon chemical shifts were computed for the gas and solvated phases. Besides using the TD-DFT, the Hirshfeld surface and Molecular Electrostatic Potential surfaces were obtained and evaluated to understand the electronic properties. The Total and partial density of state (TDOS and PDOS) spectra were also examined. All obtained computational results were compared with the previously reported experimental data. A high accuracy was obtained for the ground state geometrical structure, and thus, the vibrational frequencies especially lie on the finger print region are predicted also with a high correlation. Similarly, the optimization of chemical shift values calculated by considering solvent effects with experimental data were found as high R2 values of 0.9953 and 0.9455 for C and H atoms, respectively. This comparison shows that the DFT method precisely predicts capsaicin's molecular and spectroscopic characteristics.Öğe Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding(Walter De Gruyter Gmbh, 2021) Aygun, Bunyamin; Sakar, Erdem; Karabulut, Abdulhalik; Alim, Bunyamin; Sayyed, Mohammed, I; Singh, Vishwanath P.; Yorgun, Nergiz YildizIn this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.Öğe Evaluation of photon interaction parameters of Anti-HIV drugs(Pergamon-Elsevier Science Ltd, 2022) Akbaba, Ugur; Sakar, Erdem; Sayyed, M. I.; Alim, Bunyamin; Ozpolat, Ozgur FiratMedical treatment inevitably exposes individuals to radiation, including those taking drugs used to treat and prevent human immunodeficiency virus (HIV). Motivated by this, we investigated the radiation interaction properties of several HIV drugs to determine the interaction parameters, mass attenuation coefficient (MAC), atomic cross section (ACS), electronic cross section (ECS), effective atomic numbers (Z(eff)), and effective electron density (N-eff). We calculated the values using the Phy-X/PSD software in the range of 0.015-15 MeV. Additionally, we calculated the exposure build-up factor (EBF), and energy absorption build-up factor (EABF) values of the drugs up to 40 mean free path (MFP) using the geometric progression (G-P) method. From our findings, we determined that Combivir, with its relatively high heavy element content, had the highest radiation attenuation capacity, whereas the probability of Lopinavir interacting with photons was the lowest compared with the other drugs. The results of the EBF and EABF parameters, including the scattering effects, ordered the drugs opposite to the primary interaction parameters such as MAC, ACS, ECS, and Z(eff). These findings can guide the treatment process of HIV-positive patients and inform HIV prevention practices conducted alongside radiotherapy, as the interaction between radiation and a drug may cause deterioration in the drug's structure.Öğe Evaluation the gamma, charged particle and fast neutron shielding performances of some important AISI-coded stainless steels: Part II(Pergamon-Elsevier Science Ltd, 2020) Alim, Bunyamin; Sakar, Erdem; Han, Ibrahim; Sayyed, M., IThis is the second part of a two-part study on the investigation of radiation shielding performances of some important AISI-coded stainless steels (AISI-302, 304, 321 and 430). Part 1 addressed experimental evaluation by means of measured photon-material interaction parameters. In this second part, we focused on the calculation and discussion of other interaction parameters, which are a guide to choice optimum shielding materials in the nuclear processes for the present AISI-coded stainless steels. The present stainless steels have superior mechanical properties, high temperature and corrosion resistances and these properties can make them favorite materials for nuclear applications. For this reason, firstly, the incoherent scattering/total attenuation ratio (R-inc/total) and equivalent atomic number (Z(eq)) were calculated in the energy region of 0.015-15 MeV. Secondly, the exposure build-up factor (EBF) and energy absorption build-up factor (EABF) were determined to select steels by using Geometric Progression (G-P) fitting method, which have five parameters (a, b, c, d and X-k coefficients), up to penetration depth of 40 MFP at energy 0.015-15 MeV. Thirdly, the mass stopping powers (MSPs; dE/rho dx ; MeVcm(2)/g) and ranges (R-e, R-p and R alpha; mu m) for electron, proton and alpha particle interactions were calculated at energy 10 keV-20 MeV. Finally, the fast neutron removal cross-sections (FNRCSs; Sigma R; cm(-1)) were calculated. To be able to make comparison and a satisfying assessment about radiation shielding capabilities of present AISI-coded steels, all parameters were also computed for ordinary (OC), steel-scrap (SS) and steel-magnetite (SM) concretes (Fe-based steel concretes) that are most commonly used as a shielding material in many nuclear applications. The shielding capabilities of the present stainless steels against both gamma and the fast neutron and charged particle radiation were evaluated in the light of the calculated parameters. As a result of the mutual evaluation of the results obtained for the shielding concretes and the examined stainless steels, it was found that present stainless steels had excellent shielding properties compared to shielding concretes in terms of both photon radiation and particle radiation.Öğe Experimental investigation of radiation shielding performances of some important AISI-coded stainless steels: Part I(Pergamon-Elsevier Science Ltd, 2020) Alim, Bunyamin; Sakar, Erdem; Baltakesmez, Ali; Han, Ibrahim; Sayyed, M., I; Demir, LutfuThe investigation of radiation shielding performances of AISI-302, 304, 321 and 430 stainless steels which have wide range of application because of their superior mechanical properties, temperature and corrosion resistances was aimed in this study. In accordance with this purpose, photon-shielding parameters of these stainless steels were calculated both experimentally and theoretically. These parameters calculated are linear attenuation coefficient, mass attenuation coefficient, mean free path, half-value layer, quarter-value layer, tenth-value layer, total atomic cross-section, total electronic cross-section, effective atomic number, effective electron number and effective conductivity. They were experimentally measured at twenty-three different energies in the range 22 keV and 1333 keV. The photon energies were obtained from seven different radioactive sources (Na-22,Co- 60, Am-24(1) (109)cd , (137)cs, Eu-152 and Ba-133) . The Si(Li) and NaI(Tl) detectors were separately used taking into account of energy-efficient regions to counting process at narrow-beam transmission geometry. In addition, all these parameters were computed at the 15 keV-15 MeV wide energy range, theoretically. In order to make a satisfying assessment about radiation shielding capabilities of AISI 302, 304, 321 and 430 alloys, all calculations were also made for ordinary, steel-scrap and steel-magnetite concretes (Fe-based steel concretes) that are most commonly used as shielding material in many nuclear applications. According to the results obtained, it was observed that the radiation shielding performances of AISI 300 austenitic stainless steel series with containing Ni are superior to that of both AISI 430 ferritic stainless steel and examined concretes.Öğe An extensive survey on radiation protection features of novel hafnium iron-borophosphate glasses: Experimental and theoretical study(Pergamon-Elsevier Science Ltd, 2023) Sakar, Erdem; Alim, Bunyamin; Ertap, Huseyin; Karabulut, MevlutThis study aimed to determine the radiation (photon and particle) attenuation abilities of Hf added iron-borophosphate glasses considered as a candidate host matrix for Pu containing nuclear waste. Experimental absorption parameters were measured using 133Ba radionuclide for photon radiation, and the same parameters were theoretically calculated using Phy-X/PSD. The obtained data were evaluated comparatively for all glasses depending on the Hf and B contents. It has been determined that all of the glasses examined have photon ab-sorption ability at a level that can be a shielding material for nuclear applications. In addition, the interaction cross-sections with particle radiations were computed using SRIM and ESTAR software. When the data obtained are evaluated thoroughly, it can be said that investigated glasses can be used as shielding in areas that require protection from both photon and particle radiation, in addition to being a candidate material for the vitrification of nuclear wastes containing Pu.Öğe Investigation of neutron and gamma radiation protective characteristics of synthesized quinoline derivatives(Taylor & Francis Ltd, 2020) Aygun, Bunyamin; Alaylar, Burak; Turhan, Kadir; Sakar, Erdem; Karadayi, Mehmet; Abu Al-Sayyed, Ibrahim; Pelit, EmelPurpose: Quinoline is formed by various natural compounds, such as alkaloids from the cinchona plant, which exhibit various biological activities, and is an important building material for the development of new drugs. Quinoline can be used in anti-radiation drug development but radiation interaction properties must be determined. Material and methods: In this study, six types of synthesized quinoline derivatives were used. Fast neutron removal cross-section, mean free path, half value layer and transmission number were theoretically determined by using GEometry ANd Tracking 4 and FLUktuierende KAskade simulation codes for neutron shielding. Neutron dose absorption rates were determined using the(241)Am-Be fast neutron source and the Canberra NP series portable BF(3)gas proportional neutron detector. Gamma radiation shielding parameters were determined by using WinXCom and PSY-X/PSD software. Additionally, the genotoxic potentials of the derivatives were assessed by using the Ames/Salmonellabacterial reversion assay. Results and conclusions: Neutron shielding parameters such as removal cross-section, mean free path, half value layer and transmission number were theoretically determined for fast neutrons. To determine neutron absorption capacity of quinoline derivatives, neutron absorption, experiments were conducted. In addition, gamma radiation shielding parameters were calculated such as the mean free path (MFP), mass attenuation coefficient (mu t), half value thickness layer (HVL) and effective atomic number (Zeff) in the energy range of 0.015-15 MeV. The results of the all quinoline derivatives have excellent fast neutron shielding power compared to ordinary concrete. In addition, all quinoline derivatives have been found to have the capacity to attenuate gamma radiation. Moreover, they absorb well in both types of radiation, do not cause secondary radiation, and they are genotoxically safe at the tested concentrations. This study has demonstrated that these products can be used as active ingredients for a drug to be developed against radiation.Öğe MoO3 reinforced Ultra high molecular weight PE for neutrons shielding applications(Pergamon-Elsevier Science Ltd, 2020) Sayyed, M., I; Abdalsalam, Alyaa H.; Taki, Malaa M.; Mhareb, M. H. A.; Alim, Bunyamin; Baltakesmez, Ali; Sakar, ErdemStructural, Morphological and neutron attenuation properties of ultrahigh molecular weight polyethylene (UHMWPE) reinforced with molybdenum trioxide composite material obtained by solid state mixing of pellets and powder components via hot pressing have been studied. In this work, Ultra high molecular weight poly-ethylene and MoO3 has been utilized with different concentration using a hot compression iron mold. The changes in the microstructure of the prepared polymer and its particulate composites were evaluated by SEM. In order to investigate the quantitative of all elements used in these samples, we utilized Energy-dispersive X-ray spectroscopy (EDX) to present the profiles of synthesized samples which show a clear peaks C (carbon), and Mo (Molybdenum). The X-ray diffraction of all samples was examined to study the modification of the phase and lattice for UHMWPE before and after the addition of molybdenum trioxide (MoO3). Raman analysis was utilized to explore the crystallinity, molecular interactions, phase, polymorphy, and chemical structure. This technique is based on non-destructive interaction between light with the chemical bonds inside a material. The Raman spectrum for the current work presented within the range of 150-1600 cm(-1). In order to understand the neutron shielding performance for the fabricated UHMWPE with different concentrations of MoO3, 241 Am/Be fast neutron source was used to determine the fast neutron radiation equivalent dose rate. The background absorbed dose rate was measured as 0.98 (+/- 0.017) (mu Sv/h). It was seen that the addition of MoO3 into the UHMWPE enhances the neutron shielding. The dose released from the source was absorbed by 7.71 ( +/- 1.3) %, 18.48 (+/- 2.9) %, 22.26 (+/- 2.4) %, 24.07 (+/- 1.8) % and 26.17 (+/- 1.3) % from UHMWPE with 1, 2, 3, 4 and 5% of MoO3 respectively. Additionally, GEANT4 10.02. p01 version was used to calculate total macroscopic crosssections (TMCS) for the MoO3 doped UHMWPE. According to the results obtained from GEANT4, it was observed that the TMCS values of the UHMWPE increase with increment of the mole fraction of the MoO3 in the structure of UHMWPE examined and that the 5.0% MoO3 sample has the best neutron shielding ability.Öğe Phy-X / PSD: Development of a user friendly online software for calculation of parameters relevant to radiation shielding and dosimetry(Pergamon-Elsevier Science Ltd, 2020) Sakar, Erdem; Ozpolat, Ozgur Firat; Alim, Bunyamin; Sayyed, M. I.; Kurudirek, MuratA user friendly online Photon Shielding and Dosimetry (PSD) software available at https://phy-x.net/PSD has been developed for calculation of parameters relevant to shielding and dosimetry. These parameters include linear and mass attenuation coefficients (LAC, MAC), half and tenth value layers (HVL, TVL), mean free path (MFP), effective atomic number and electron density (Z(eff), N-eff), effective conductivity (C-eff) energy absorption and exposure buildup factors (EABF, EBF). The software can generate data on shielding parameters in the continuous energy region (1 keV-100 GeV). Also, some well-known radioactive sources ( Na-22, Fe-55, Co-60, Cd-109, I-131, Ba-133, Cs-137, Eu-152 and Am-241) along with their energies and some characteristic (K-shell) X-ray energies of Cu, Rb, Mo, Ag, Ba and Tb elements are available in the software and can be selected by the user. Thus, one can obtain the shielding parameters at photon energies available for the predefined energies. Moreover, another parameter relevant to shielding i.e. the fast neutron removal cross section (FNRCS) can be calculated for a compound or a mixture using this software. The software is freely available online after having registered to the Phy-X platform.Öğe Precipitation-hardening stainless steels: Potential use radiation shielding materials(Pergamon-Elsevier Science Ltd, 2022) Alim, Bunyamin; Ozpolat, Ozgur Firat; Sakar, Erdem; Han, Ibrahim; Arslan, Ibrahim; Singh, V. P.; Demir, LutfuIn this study, it was focused on the research of new materials with high attenuation efficiency that can be used as radiation shielding material due to the incapability of conventional materials. In accordance with this purpose, the radiation shielding capabilities of four different precipitation-hardening stainless steels (PH-SSs), which are symbolized 15-5PH, 15-7PH, 17-4PH and 17-7PH, were determined both experimentally and theoretically in a wide range of radiation energy. For experimental measurements, two different detectors (Si(Li) and Na(Tl)) and twenty-three different photon energies (from 22.1 to 1332.5 keV) emitted from seven different radionuclides were used in narrow-beam transmission geometry. Phy-X/PSD software were used for theoretical calculations. The theoretically calculated parameters were determined both in the photon energies emitted by the radionuclides used in the experiment and in the continuous energy range of 0.015-15 MeV. Furthermore, in order to make a remarkable assessment of the integration of PH-SSs to nuclear energy applications, the all results obtained have been compared with the corresponding values of Fe-based steel concretes (steel-scrap (SS) and steel magnetite (SM)), which are widely used as conventional shield materials in nuclear power plants. Moreover, in order to choose the best material to be used in nuclear applications among the PH-SSs, the results were evaluated comparatively in terms of both the characteristics of the materials and the magnitude of the radiation shielding parameters. Consequently, it was concluded that the material with the best radiation shielding performance among the examined PH-SSs was 15-7PH and the radiation shielding performance ranking was generally in the form of 15-7PH >= 15-5PH > 17-4PH > 17-7PH > SM > SS. Due to both high attenuation efficiency and superior properties for radiation shielding, it was determined that the PH-SSs can be used as new shielding materials in nuclear applications.Öğe A study of gamma attenuation property of UHMWPE/Bi2O3 nanocomposites(Elsevier, 2019) Abdalsalam, Alyaa H.; Sayyed, M., I; Hussein, Thulfiqar Ali; Sakar, Erdem; Mhareb, M. H. A.; Sakar, Betul Ceviz; Alim, BunyaminIn this study, nanocomposite material made of ultra-high molecular weight and bismuth oxide was developed to be used for protection from nuclear radiation. The traditional hot-pressing technique was used for preparing composite samples. The concentrations of Bi2O3 were selected to be 0.5, 1.0, 1.5, 2.0 wt%. In order to study the changes in surface morphology, we examined all samples by scanning electron microscopic (SEM). We evaluated the semi-quantitative of all elements used to fabricate these samples using EDX. Additionally, all samples including pure Bi2O3 has been examined with X-ray diffraction (XRD). Besides that, Raman spectroscopy of all synthesized polymer matrix was measured to explore the different molecular groups. Also, the photon attenuation ability for the present samples was measured experimentally at eight energies varying from 30.8 keV to 383.9 keV using Ba-133 radioactive point source.Öğe A surveying of photon and particle radiation interaction characteristics of some perovskite materials(Pergamon-Elsevier Science Ltd, 2021) Sakar, Erdem; Alim, Bunyamin; Ozpolat, Ozgur Firat; Sakar, Betul Ceviz; Baltakesmez, Ali; Akbaba, UgurIn this study, we aimed to determinate of the photon and particle radiation interaction parameters of six different perovskites to help use perovskite materials in radiation applications. The parameters that are aimed to be investigated are MAC, HVL, MFP, Z(eff), N-eff, C-eff and EBF for photons, range values for charged particles, and FNRCS values for neutrons. The photon-interaction parameters the FNRCS values of the perovskites were calculated using Phy-X/PSD software in the energy range of 1 keV-100 GeV for photons and at 4.5 MeV energy for neutrons, respectively. Moreover, the range values of the perovskites were calculated using SRIM Monte Carlo software (for H+ and He++ particles) and ESTAR NIST software (for electrons) in the energy range from 0.01 MeV to 20 MeV. In order to make a notable assessment about the radiation interaction possibilities of the perovskites, the results obtained were compared with some standard shielding materials. According to the results obtained for all radiation types examined, it was determined that all calculated parameters were strongly dependent on both the type and energy of the radiation and the type of material. Additionally, it was observed that the order of preference of the examined materials as armor material in radiation applications varies according to the radiation type and energy. Consequently, it was determined that while the most suitable material in terms of photon shielding is P6 (Cs2SnI6) inorganic perovskite among the perovskites examined, this sample is not suitable material for neutron shielding applications.Öğe Theoretical and experimental validation gamma shielding properties of B2O3-ZnO-MgO-Bi2O3 glass system(Elsevier Science Sa, 2020) Kaky, Kawa M.; Sayyed, M. I.; Khammas, Abbas; Kumar, Ashok; Sakar, Erdem; Abdalsalam, Alyaa H.; Sakar, Betul CevizIn the present work, we fabricated a series of six glasses to be utilized in the field of radiation shielding application. Glasses have been synthesized using a melt-quenching ordinary technique. In this work, we investigated the structural properties of these glasses using Raman spectroscopy. Moreover, optical properties have been studied in the present work. The radiation attenuation ability for the present samples was also investigated and measured using transmission geometry between 81 and 964.1 keV. The mass attenuation coefficient was measured and the results were validated by the WinXcom program. Also, radiation protection efficiency (RPE) was evaluated and discussed in terms of photon energy and Bi2O3 concentration. From RPE curve, we found that the fabricated glasses can be used as effective shielding materials especially for the low energies (81-383 keV). The half value layer also was calculated and the results of this parameter showed that S6 (contains 60 mol% of Bi2O3) has the higher probability of the interaction with gamma photons, leading to less number of photons transmitted this sample and thus better photon attenuator.
