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Öğe 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.Öğe A study on radiation interaction parameters of boron carbide/zirconium boride composites(Springer Heidelberg, 2025) Turhan, M. F.; Tursucu, A.; Ogul, H.; Kacal, M. R.; Polat, H.; Colak, E.; Yurtcan, S.In this study, photon interaction parameters such as radiation protection efficiency (RPE), total mass attenuation coefficient (mu/rho), linear attenuation coefficients (mu), half value layers (HVL), tenth value layers (TVL), mean free paths (MFP), effective atomic numbers (Z(Eff)) and effective electron densities (N-Eff) were experimentally investigated for the BCZrB-0, BCZrB-10, BCZrB-20, BCZrB-30, BCZrB-40 and BCZrB-50 in the energy range from 59.5 keV to 1332.5 keV. In the experiment, HPGe detector and Am-241 (59.5 keV), Ba-133 (81 keV, 276.4 keV, 302.9 keV, 356 keV and 383.9 keV), Na-22 (511 keV and 1274.5 keV), Cs-137 (661.7 keV), and Co-60 (1173.2 keV and 1332.5 keV) radioactive point sources were used. Experimental results compared with results of the WinXCOM, GEANT4 simulation code and FLUKA simulation code. Energy absorption build-up factors (EABF) and exposure build-up factors (EBF) were calculated with G-P fitting method in the energy region 0.015 MeV <= E <= 15 MeV. Kerma relative to air values were investigated in the energy region 0.001 MeV <= E <= 20 MeV. Effective removal cross section, total macroscopic cross section and number of transmitted neutron values were defined for composites. The agreement between experimental and WinXCOM program, between experimental and GEANT 4 simulation codes and between experimental and FLUKA simulation codes of gamma-ray interaction parameters are < 5.1%, < 6.5% and < 5%, respectively. All of the results are compatible with each other and BCZrB-50 is a good gamma-ray radiation absorber in the studied composites and BCZrB-0 is the best neutron absorber in the studied composites.Öğe 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.Öğe Impact of lead(II) iodide on radiation shielding properties of polyester composites(Springer Heidelberg, 2020) Akman, F.; Ogul, H.; Kacal, M. R.; Polat, H.; Dilsiz, K.; Turhan, M. F.This paper investigates the radiation shielding properties, such as linear and mass attenuation coefficients, half and tenth value layers, effective atomic number and electron density, and radiation protection efficiency as a function of photon energy, of a new composite, PbI2-doped polyester. The mentioned polyester composite was prepared with different proportions of lead(II) iodide (5% increments between 5 and 20%) so that impact of the dopant amount on radiation shielding could be properly analyzed. The prepared composites were tested in 22 different energies in the energy range of 59.5-1408.0 keV with the use of HPGe detector and eight radioactive point sources. The obtained results were further validated by comparing the results of XCOM computer program, and negligible discrepancies were observed. It was observed that PbI2 (20%) composite is more effective gamma radiation shielding material than other produced composites. In light of this information, it can be said that the shielding efficiency increases with increasing lead(II) iodide amount.












