Yazar "Ozdogan, H." seçeneğine göre listele

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    A study on photon/neutron interaction parameters with some alloys implant frequently used in orthopedics
    (Pergamon-Elsevier Science Ltd, 2025) Akman, F.; Turhan, M. F.; Ogul, H.; Ozdogan, H.; Turhan, M. K.
    Some Ti and Co-based alloys are used for implant purposes in orthopedics. These implants may cause artifacts during imaging in radiology. These may cause image quality to deteriorate due to glare in the relevant area. In the presented study, radiation protection efficiency (RPE), mass attenuation coefficient (mu/rho, MAC), linear attenuation coefficient (mu, LAC), half value layer (HVL), mean free path (MFP), tenth value layer (TVL), effective atomic number (Zeff) at 30-150 keV, energy-absorption build-up factor (EABF) and exposure build-up factor (EBF) at 0.015-15 MeV and kerma relative to air parameters at 0.001-20 MeV were obtained for some Ti and Cobased alloys, which frequently used in orthopedics. Photon interaction parameters were calculated using WinXCOM, MCNP6, PHITS, FLUKA and GEANT4 methods. EABF, EBF and kerma relative to air parameters were investigated theoretically with the help of WinXCOM. In addition, to investigate the neutron interaction parameters of these implants, RPE values at different thicknesses at 4.5 MeV with FLUKA, total macroscopic cross section and mean free path with GEANT4 and effective removal cross section for fast neutron with theory were obtained. Mass attenuation coefficients for the Ti-based alloys and Co-based alloys were determined as in the range from 0.159 cm2 g- 1 to 6.466 cm2 g- 1 and 0.200 cm2 g- 1 to 10.791 cm2 g- 1 in the energy range from 30 keV to 150 keV, respectively. It has been observed that among TiAl6V, Ti6Al7Nb, Grade1, Co28Cr6Mo, Co20Cr15W10Ni and Co35Ni20Cr10Mo implants, Co20Cr15W10Ni has the best attenuation ability for photons and neutrons.
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    Assessment of neutron and gamma-ray shielding characteristics in ternary composites: Experimental analysis and Monte Carlo simulations
    (Pergamon-Elsevier Science Ltd, 2024) Akman, F.; Kilicoglu, O.; Ogul, H.; Ozdogan, H.; Kacal, M. R.; Polat, H.
    The research aims to exploring the gamma -ray shielding capacities of polyacrylonitrile/chrome-filled polymer composites through a combination of experimental, theoretical and simulation methods. Additionally, employing MCNPv6 and GEANT4 simulation tools, the study evaluates the materials' performance against neutron radiation. The materials were subjected to various gamma -ray energy levels, and their shielding efficacies are analytically quantified using parameters such as Radiation Protection Efficiency (RPE), Mass Attenuation Coefficient (MAC), Linear Attenuation Coefficient (LAC), and Half -Value Layer (HVL). At various neutron energies and sample thicknesses, the numbers of transmitted neutrons were evaluated. Notably, composite P0Cr50 (not contain polyacrylonitrile and containing 50% chromium) emerges prominently, demonstrating superior radiation shielding characteristics against both gamma and neutron radiations. This attitude is attributed to its optimal chrome dispersion and density, positioning it as a promising candidate for radiation shielding applications in industrial and nuclear domains.
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    Determination of neutron and gamma ray shielding properties, secondary radiation formations and neutron damage of composites containing polyester/pyrite/titanium diboride
    (Pergamon-Elsevier Science Ltd, 2025) Turhan, M. F.; Kacal, M. R.; Ozdogan, H.; Tursucu, A.; Akman, F.; Ogul, H.; Polat, H.
    Composite materials comprising titanium diboride (TiB2), unsaturated polyester resin, and pyrite (FeS2) at varying weight percentages were fabricated and evaluated for their interaction with neutron and gamma radiation. This study adopts a comprehensive methodology, combining theoretical calculations, experimental measurements, and Monte Carlo simulations using PHITS and MCNP6. A strong correlation was observed among experimental results, WinXCOM data, and simulation outputs, with discrepancies remaining within approximately 5 %. To assess neutron shielding performance, fast neutron removal cross sections and partial neutron transmission rates were determined for both fast and thermal neutron energies, as well as across varying sample thicknesses. Additionally, secondary radiation effects were analyzed by quantifying the number and average energy of secondary neutrons and gamma photons generated from interactions with thermal and fast neutrons. Radiation damage parameters, including Total Ionizing Dose (TID) and Displacement Per Atom (DPA), were also evaluated. Gamma-ray shielding performance was assessed through experimental measurements, theoretical models, and Monte Carlo simulations, focusing on key parameters such as mass attenuation coefficients, kerma relative to air and concrete, and buildup factors. Among the composites, the sample labeled FeSTiB-50 demonstrated superior fast neutron attenuation capability-outperforming conventional concrete and approaching the shielding efficiency of paraffin-while all composites exhibited excellent attenuation of thermal neutrons. Furthermore, the FeSTiB-50 composite generated secondary radiation with lower average energy compared to other samples. However, the gamma-ray shielding performance was found to decrease with increasing TiB2 content, indicating a trade-off between neutron and gamma shielding effectiveness.
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    Experimental, simulation, and theoretical investigations of gamma and neutron shielding characteristics for reinforced with boron carbide and titanium oxide composites
    (Pergamon-Elsevier Science Ltd, 2025) Ozdogan, H.; Kacal, M. R.; Kilicoglu, O.; Polat, H.; Ogul, H.; Akman, F.
    This study investigates the radiation shielding properties of composites containing polyester resin, boron carbide and titanium oxide in varying proportions. The radiation transmittance of the produced composites was measured using radioactive sources Am-241, Cs-137, Ba-133, Co-60, and Na-22 across a photon energy range of 59.5 keV-1332.5 keV. To analyze radiation permeability, experimental geometry was simulated using Monte Carlo-based computer codes Monte Carlo N-Particle (MCNP), Particle and Heavy Ion Transport code System (PHITS) and FLUktuierende KAskade or Fluctuating Cascade (FLUKA), and the experimental data were compared with simulation results and theoretical data obtained from WINXCOM. The findings demonstrated a high degree of consistency between experimental, simulation, and theoretical results. Notably, the BCTiO50 sample, which included a 50% addition of TiO2, emerged as the most effective in photon radiation shielding. In addition to gamma shielding, the neutron shielding properties of the produced composites were evaluated using the FLUKA code, revealing that the BCTiO0 sample, with the highest percentage of boron, provided the best neutron shielding. This analysis included composites with decreasing boron carbide content by 10%, 20%, 30%, 40%, and 50% by weight, each replaced with titanium oxide, showcasing the potential applications of these polymer composites in radiation shielding.
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    Gamma, charged particle and neutron radiation shielding capacities of ternary composites having polyester/barite/tungsten boride
    (Pergamon-Elsevier Science Ltd, 2023) Akman, F.; Ozdogan, H.; Kilicoglu, O.; Ogul, H.; Agar, O.; Kacal, M. R.; Polat, H.
    The presented work investigates the photon, charged particle and neutron radiation shielding performances of polyester-based composites filled with barite and/or tungsten boride by using experimental, theoretical, and Monte Carlo simulation techniques. The amount of barite/tungsten boride varying from 0 wt% to 50 wt% in the material and polyester resin were exploited as filler and base materials, respectively. Experimental evaluation of BaWB composites has been performed with help of an HPGe detector based gamma spectrometer as well as 22Na, 133Ba, 137Cs and 60Co radioactive point sources with energies in the range of 276.4-1332.5 keV. The experimental data were compared to those theoretically calculated in WinXCOM as well as Monte Carlo (MC) simulations, i.e., MCNP6, GEANT4 and FLUKA codes. The obtained mass attenuation coefficients for the produced composites were in good agreement with the results of MC simulations and WinXCOM software. Comparing to the other polymer composite samples, the sample with the maximum tungsten boride weight percentage has the best radiation shielding property because of having the highest attenuation coefficients and lowest absorption thicknesses.