Sürdürülebilir Kalkınma Amaçları

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• MakaleAçık Erişim2026Scopus SJRQ2/r/bayburt/11423
  Investigation of radiation shielding parameters of AZ61 magnesium alloy after electric arc spray and micro arc oxidation processes

  Durna, İdris; Yılmaz, Demet; Çatar, Recep; Altun, Hikmet

  In this study, the radiation shielding parameters of AZ61 magnesium (Mg) alloy, which is used in automotive, aerospace, and biomedical fields due to its low density, high specific strength, and biocompatible properties, were determined to investigate its usability in nuclear protection applications. Firstly, Al coating was applied to AZ61 Mg alloy by electric arc spray process and then ceramic oxide layer was obtained by micro arc oxidation (MAO) method. Then, the radiation shielding properties of AZ61 alloy were investigated. The radiation shielding parameters such as mass attenuation coefficient (MAC), mean free path (MFP), half-value layer (HVL) and effective atomic numbers (Zeff) were measured in gamma spectrometer with Ba-133 radioactive sources. The fast neutron removal cross-sections (ΣR), exposure buildup factors (EBF) were theoretically determined. The results revealed that the duplex coating (AZ61-Al-O) significantly enhanced the gamma shielding capability compared to the uncoated AZ61 alloy, achieving about 8.0 % higher MAC at 383.8 keV. Therefore, the AZ61-Al-O sample can be considered a promising lightweight material for radiation protection applications.

  AtıfScopus3·WoS3·OpenAlex4

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• MakaleYalnız künye2023Scopus SJRQ2/r/bayburt/11763
  Prediction of gamma ray spectrum for 22Na source by feed forward back propagation ANN model

  Teke, Cagatay; Akkurt, Iskender; Arslankaya, Seher; Ekmekci, Ismail; Gunoglu, Kadir

  The radiation has been used in a variety of different fields since its discovery and thus its measurement becomes vital in these industries. Different type detector may be used to measure gamma rays depends on the purposes of measurements. Gamma ray energy spectrum is an important to determine either elemental analysing of a sample or radiation shielding purposes. On the other hand, Artificial Neural Network (ANN) may be used to predict and analysing of gamma-ray spectrum. In this study, gamma ray spectrum from 22Na source detected in NaI (Tl) detector was estimated by ANN. There have been installed ten different ANN models to find the network structure that produces the best predictive value for the gamma ray spectrum NaI (Tl) Detector. Estimation study has been continued with the ANN model with be possessed of lowest error value. ANN model was created by using energy, distance and gamma-rays energy spectrum (called Io) values. In the ANN model developed using the feed forward back propagation algorithm, were used artificial neurons two in the input layer, ten in the hidden layer and one in the output layer. For the case of present work, the experimental data was used 70% for education, 20% for validation and 10% for testing. The estimated values obtained with the ANN model were compared with the experimental results and a good correlation has been found between them (R2 = 0.99).

  AtıfScopus18·WoS9·OpenAlex27

  İncele
• MakaleAçık Erişim2023Scopus SJRQ2/r/bayburt/11012
  Determination of the molecular structure and spectroscopic properties of capsaicin

  Çınar, Mehmet; Alım, Bünyamin; Alım, Zuhal; Şakar, Erdem

  In 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.

  AtıfScopus16·WoS16·OpenAlex15

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• MakaleAçık Erişim2022Scopus SJRQ2/r/bayburt/13441
  Precipitation-hardening stainless steels: Potential use radiation shielding materials

  Alım, Bünyamin; Özpolat, Özgür Fırat; Şakar, Erdem; Han, İbrahim; Arslan, İbrahim; Singh, V.P.; Demir, Lütfü

  In 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.

  AtıfScopus25·WoS25·OpenAlex27

  İncele
• MakaleYalnız künye2022Scopus SJRQ2/r/bayburt/13347
  Evaluation of γ-rays and neutron shielding parameters of high dense bismo-boro-tellurite glasses: Comparative study

  Şakar, E.; Özpolat, Ö.F.; Alım, B.; Alsaif, Norah A.M.; Rammah, Y.S.

  The main high energy radiation-matter interaction parameters of the 30B2O3-(70-x)TeO2-xBi2O3, where x = 40, 50, 60 and 70 mol% (BTB) glasses have been studied in the wide energy range. The theoretical calculations were made for some special X and γ-ray energies emitted from Fe (55), Am (241), Cs (137) and Co (60) radioactive sources for photon energies in the range of 15 keV - 15 MeV. All evaluated radiation shielding parameters were compared with some selected concretes (Ordinary concrete (OC), Hematite-Serpenite (HS) and Basalt-Magnetide (BM)), and glasses (Te and Pb based). The BTB- glasses have higher mass attenuation coefficient (MAC) values than other glasses (Te and Pb based) and concretes (OC, HS, and BM). The half value layer (HVL) of the investigated BTB-glasses has the following trend: OC > HS > BM > Te-Glass > Pb-glass > BTB40 > BTB50 > BTB60 > BTB70. In terms of mean free path (MFP), the BTB70 coded glass has the lowest MFP values due to the highest Bi2O3 content. In terms of the Zeff values of BTB coded glasses vary between 70 and 75 at the lowest energy level. The effective atomic number (Zeff) values in this energy region were 48.974 and 63.102 for Te and Pb glasses, respectively, and 13,339, 15.520 and 15.894 for OC, HS and BM concretes. The BTB-coded glasses have lower exposure buildup factor (EBF) than all other glass and concrete up to 3 MeV photon energies. The energy absorption buildup factor (EABF) values range from 1 to 4.2 for all samples at 1 MFP and at 40 MFP values, it reaches 108 for BTB coded glasses and 1010 for Te-based glass. Results confirmed that BTB- glasses, especially BTB70 glass sample can be used in applications requiring radiation safety.

  AtıfScopus17·WoS16·OpenAlex17

  İncele
• MakaleYayıncıda açık erişim2022Scopus SJRQ2/r/bayburt/12862
  Evaluation of photon interaction parameters of Anti-HIV drugs

  Akbaba, Uğur; Şakar, Erdem; Abu Al-Sayyed, Mohammed Ibrahim; Alim, Bünyamin; Özpolat, Özgür Fırat

  Medical 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 (Zeff), and effective electron density (Neff). 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 Zeff. 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.

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  AtıfScopus9·WoS8·OpenAlex12

  İncele
• MakaleYalnız künye2021Scopus SJRQ2/r/bayburt/14257
  An online software to simulate the shielding properties of materials for neutrons and photons: NGCal

  Gökçe, H. S.; Güngör, O.; Yilmaz, H.

  NGCal, a free online computation software (http://ngcal.com), has been developed for narrow beam transmission properties of photons (for energies of X rays and gamma rays between 0.002 MeV and 20 MeV), thermal (25.4 meV) and fast neutrons (4 MeV), in this regard it theoretically calculates the mass and linear attenuation coefficient/factor, mean free path, half- and tenth-value layers of materials formed by elements, compounds and composites. Its calculation assumptions, user guide as well as a comparative example of its results to those of other online computation platforms (XCOM, NCNR, WinXCOM, MCNPX, and Phy-X/PSD) are presented in this study. The developed software allows for more data input consisting of elements/oxides/compound and their fractions, and presents a number of shielding results required by researchers and scientists working on radiation shielding properties of multi-component materials.

  AtıfWoS85·OpenAlex93

  İncele
• MakaleAçık Erişim2021Scopus SJRQ2/r/bayburt/11967
  A surveying of photon and particle radiation interaction characteristics of some perovskite materials

  Şakar, Erdem; Alim, Bünyamin; Fırat Özpolat, Özgür; Ceviz Şakar, Betül; Baltakesmez, Ali; Akbaba, Uğur

  In 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, Zeff, Neff, Ceff 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.

  AtıfScopus27·WoS25·OpenAlex26

  İncele
• MakaleYalnız künye2020Scopus SJRQ2/r/bayburt/13490
  Study on the radiation attenuation properties of locally available bees-wax as a tissue equivalent bolus material in radiotherapy

  Islam, Sazirul; Mahmoud, K.A.; Sayyed, M.I.; Alim, Bünyamin; Rahman, Md.M.; Mollah, A.S.

  In radiation therapy field, bolus material is frequently utilized when treating different areas of a patient, like at the ears or nose, and to provide build-up of dose to the skin surface. The bolus material must be cost effective, suitably flexible to conform to the surface of the patient, and most importantly should be tissue equivalent. The main objective of this work was to estimate the photon attenuation properties of locally available bees-wax and to assess the feasibility of using this bees-wax as a bolus material practice for treatment of cancer patient. The mass attenuation coefficient (μ/ρ) values have been calculated by using MCNP5 simulation code over the wide range of photon energy (0.015–10 MeV). Some related parameters such as the effective atomic number and the mean free path were also calculated to understand the photon attenuation ability of the investigated bolus material. The attenuation properties were also computed for water, tissue and commercial bolus materials for comparison. Evaluation of the results showed that the radiation attenuation properties of locally available bees-wax have a good similarity to water/tissue. Referring to the results of this study, it is proposed that locally available bees-wax is a suitable substance to be used as bolus material practice for treat of cancer patient.

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  AtıfScopus59·WoS53·OpenAlex63

  İncele
• MakaleYalnız künye2020Scopus SJRQ2/r/bayburt/13440
  MoO3 reinforced Ultra high molecular weight PE for neutrons shielding applications

  Sayyed, M.I.; Abdalsalam, Alyaa H.; Taki, Malaa M.; Mhareb, M.H.A.; Alim, Bünyamin; Baltakesmez, Ali; Şakar, Erdem

  Structural, 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 polyethylene 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, 241Am/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) (μSv/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 cross-sections (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.”

  AtıfScopus55·WoS54·OpenAlex57

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