Yazar "Ogul, H." seçeneğine göre listele

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    A comparative neutron and gamma-ray radiation shielding investigation of molybdenum and boron filled polymer composites
    (Pergamon-Elsevier Science Ltd, 2023) Ogul, H.; Agar, O.; Bulut, F.; Kacal, M. R.; Dilsiz, K.; Polat, H.; Akman, F.
    This work presents a detailed radiation shielding study for polymer composites filled with Boron and Molyb-denum additives. The chosen novel polymer composites were produced at different percentages of the additive materials to provide a proper evaluation of their neutron and gamma-ray attenuation abilities. The effect of additive particle size on the shielding characteristics was further investigated. On the gamma-ray side, simula-tion, theoretical and experimental evaluations were performed in a wide range of photon energies varying from 59.5 keV to 1332.5 keV with help of MC simulations (GEANT4 and FLUKA), WinXCOM code, a High Purity Germanium Detector, respectively. A remarkable consistency was reported between them. On the neutron shielding side, the prepared samples produced with nano and micron particle size additives were additionally examined by providing fast neutron removal cross-section (sigma R) and the simulated neutron transmissions through the prepared samples. The samples filled with nano sized particles show better shielding capability than the one filled with micron sized particles. In other words, a new polymer shielding material that does not contain toxic content is introduced: the sample codded N-B0Mo50 exhibits superior radiation attenuation.
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    A detailed investigation of gamma and neutron shielding capabilities of ternary composites doped with polyacrylonitrile and gadolinium (III) sulfate
    (Pergamon-Elsevier Science Ltd, 2023) Erkoyuncu, I. .; Akman, F.; Ogul, H.; Kacal, M. R.; Polat, H.; Demirkol, I.; Dilsiz, K.
    The shielding efficiencies of gamma and neutron radiations for ternary composites containing polyester resin, polyacrylonitrile and gadolinium (III) sulfate at different ratios were investigated in the present study. In order to investigate the gamma radiation shielding capacity of the produced ternary composites, linear and mass atten-uation coefficients, half value layer, effective atomic number and radiation protection efficiency parameters were determined experimentally, theoretically and using the GEANT4 simulation code. The gamma shielding capa-bilities of the composites were studied in the photon energy range of 59.5-1332.5 keV. In order to investigate the neutron shielding abilities of composites, inelastic, elastic, capture and transport numbers, total macroscopic cross section and mean free path parameters were determined with the help of GEANT4 simulation code. In addition, the number of transmitted neutrons at different sample thicknesses and neutron energies were also determined. It was observed that gamma radiation shielding properties were improved due to the increasing amount of gadolinium (III) sulfate and neutron shielding properties were improved due to the increasing amount of polyacrylonitrile. While the composite coded P0Gd50 exhibits a better gamma radiation shielding ability than the others, the neutron shielding of the sample coded P50Gd0 is also more favorable than the others.
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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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    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.
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    A study on radiation shielding properties, secondary radiation and radiation damage for composites containing glass fiber/PEEK/ gadolinium oxide
    (Pergamon-Elsevier Science Ltd, 2026) Erkoyuncu, I.; Maroc, F. Z.; Yilmaz, M.; Torun, T. R.; Ozdemir, H. G.; Ogul, H.; Akman, F.
    This study aimed to determine the gamma and neutron shielding capacities, the number of secondary gamma and neutrons produced after the primary neutron interaction together with their average energies and the damage caused by the incident gamma and neutron radiation on the composite for the composites containing glass fiber, PEEK and gadolinium oxide (Gd2O3). The theoretical approaches and/or simulation codes such as GEEANT4/FLUKA were used to determine these properties. It was observed that the gamma shielding capacity was improved for the studied composites with increasing Gd2O3 content. It was determined that the composite containing 50 % Gd2O3 (50GF50GdO), which was the highest studied amount, was superior to the others. The same composite also exhibited superior performance in removing fast neutrons. In addition, this composite has a fast neutron removal capacity that is 0.79 times higher than paraffin and 1.77 times higher than ordinary concrete. In terms of neutron shielding, the composite containing 50 % PEEK showed better performance at low energies, while 50GF50GdO replaced with this composite at high energies. It was determined that the composite coded as 50GF50GdO was less risky than the other composites in terms of both secondary gamma and secondary neutron formation. Finally, it was observed that as the energy of both gamma and neutron radiation increased, the studied composites were exposed to more radiation damage.
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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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    Characterization of photomultiplier tubes in a novel operation mode for Secondary Emission Ionization Calorimetry
    (Iop Publishing Ltd, 2016) Tiras, E.; Dilsiz, K.; Ogul, H.; Southwick, D.; Bilki, B.; Wetzel, J.; Nachtman, J.
    Hamamatsu single anode R7761 and multi-anode R5900-00-M16 Photomultiplier Tubes have been characterized for use in a Secondary Emission (SE) Ionization Calorimetry study. SE Ionization Calorimetry is a novel technique to measure electromagnetic shower particles in extreme radiation environments. The different operation modes used in these tests were developed by modifying the conventional PMT bias circuit. These modifications were simple changes to the arrangement of the voltage dividers of the baseboard circuits. The PMTs with modified bases, referred to as operating in SE mode, are used as an SE detector module in an SE calorimeter prototype, and placed between absorber materials (Fe, Cu, Pb, W, etc.). Here, the technical design of different operation modes, as well as the characterization measurements of both SE modes and the conventional PMT mode are reported.
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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 and Neutron Shielding Parameters of Polyester-based composites reinforced with boron and tin nanopowders
    (Pergamon-Elsevier Science Ltd, 2022) Ogul, H.; Polat, H.; Akman, F.; Kacal, M. R.; Dilsiz, K.; Bulut, F.; Agar, O.
    The usage of composites as the shielding materials are highly recommended since they could be used in order to attenuate the undesired radiation with unique properties and advantages in the areas where the radiation is prevalent. In this context, not only are their radiation shielding properties important but also their flexibility, durability and low cost. Due to the mentioned superior characteristics, the polyester based composites are among the most preferred materials. With the aim of creating unique and novel radiation shielding materials, this study investigates gamma and neutron shielding capabilities of the polyester composites reinforced with Boron and Tin nanopowders at different proportions (0-50%, 10-40%, 20-30%, 30-20% and 40-10%, 50-0%). The gamma shielding abilities of the prepared polyester composite materials were evaluated using an HPGe detector system, WinXCOM computer program and different simulation tools (FLUKA and GEANT4) at the energies varying from 59.5 to 1332.5 keV. The experimental, theoretical and simulation results showed remarkable agreement between each other, and the addition of Sn enhances the gamma attenuation performance of the chosen polyester composite materials. In addition to gamma analysis results, neutron shielding properties of the proposed com-posites are further determined. On this purpose, the transmitted neutron numbers through the samples (as functions of neutron energy and the sample thickness) and effective neutron removal cross sections were eval-uated. The neutron shielding performance of the samples showed that the prepared composites could be alter-native materials to the existing neutron shields in the literature.
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    Gamma attenuation characteristics of CdTe-Doped polyester composites
    (Pergamon-Elsevier Science Ltd, 2021) Akman, F.; Ogul, H.; Kacal, M. R.; Polat, H.; Dilsiz, K.; Agar, O.
    Polyester is strong and durable material and tends to retain its shape, thus polyester composites have become highly preferred option in high-tech applications. This motivates the usage of polyester composites in the production of radiation shielding materials as well. In present study, gamma ray shielding properties of polyester composite reinforced with different proportions of Cadmium Telluride (5%, 10%, 15% and 20%) have been investigated theoretically and experimentally. The experiments were performed with the use of HPGe detector in a wide range of photon energies varying from 59.5 to 1408.0 keV while XCOM computer program was computed in the same photon energy range to obtain theoretical results and to verify the experimental outcomes. Remarkable radiation protection efficiency was obtained with additive material of Cadmium Telluride, and the radiation protection efficiency was found to be increased with the increase of additive material amount. Negligible discrepancies between experimental and theoretical results were also observed.
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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.
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    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.
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    Micro Pb filled polymer composites: Theoretical, experimental and simulation results for γ-ray shielding performance
    (Pergamon-Elsevier Science Ltd, 2022) Kilicoglu, O.; V. More, Chaitali; Akman, F.; Dilsiz, K.; Ogul, H.; Kacal, M. R.; Polat, H.
    Researches on advanced composites to protect environment health towards radioactive pollution have drawn attention with the rising use of radioactive elements. From this point, polymer micro composites are quite encouraging in terms of multifunctional properties in mechanical, electrical, thermal, as well as nuclear shielding. The present study has explored the efficacy of micro lead (Pb) loaded polymer composites for radio protective applications such as a fabrication of protective enclosures. High energetic photon shielding experiments have been applied through gamma spectrometer equipped with HPGe detector and various radioactive point sources namely 137Cs, 22Na, 152Eu, 133Ba, 241Am and 57,60Co which are widely used in several medical and industrial applications. The results demonstrated that mass attenuation coefficients of the composites at different photon energies are proportional to the filler loading. The validation of FLUKA and GEANT4 Monte Carlo software has been performed in the simulation of transmission experiments as well as WinXCOM software. The tests of the Pb (20%) micro composite for the nuclear radiation shielding reveal that it has high attenuation coefficients for photon radiation.
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    Nuclear radiation shielding performance of borosilicate glasses: Numerical simulations and theoretical analyses
    (Pergamon-Elsevier Science Ltd, 2023) Kilicoglu, O.; Akman, F.; Ogul, H.; Agar, O.; Kara, U.
    The photon shielding performances of five different borosilicate-based glasses were investigated in this study using the FLUKA, GEANT4 and MATLAB codes, as well as the XCOM program, at photon energies ranging from 0.03 to 15 MeV. In this context, dependencies of the photon attenuation features with the variation of the photon energy and the chemical compositions have been carefully evaluated with Monte Carlo simulation and theo-retical evaluation tools. The mass attenuation coefficient values and effective atomic numbers obtained for BaO-doped G5 glasses are found to be higher than those derived for G1-G4 samples. In other words, the Zeff results showed that high Z-elements such as Ba in a suitable amount should be inserted into the glass composition in order to improve the photon attenuation capability of the borosilicate glasses. The HVLs, TVLs, and MFPs of the studied borosilicate glasses are determined further, and the gamma shielding characteristics of the analyzed samples are found to be associated to the density of the glass, implying that high-density glass can be used for high-level attenuation performance. The exposure buildup factor (EBF) values have been further estimated via the G-P fitting approach. The results of such investigations, according to the work given, may be valuable in designing and fabricating new borosilicate-based glasses, which can then shield against potential radiation damage to environmental health.
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    Secondary Emission Calorimetry
    (Institute of Electrical and Electronics Engineers Inc., 2022) Bilki, B.; Dilsiz, K.; Ogul, H.; Onel, Y.; Southwick, D.; Tiras, E.; Wetzel, J.
    In high-radiation environments, electromagnetic calorimetry is particularly challenging. To address this, a feasible approach involves constructing a sampling calorimeter that employs radiation-hard active media, albeit at the expense of high energy resolution. In response, we developed an innovative technique, secondary emission calorimetry, which offers radiation resistance, rapid response, robustness, and cost-effectiveness. Our efforts involve the creation of prototype secondary emission sensors, subjected to comprehensive testing within test beams. In the secondary emission detector module, incident charged hadrons or electromagnetic shower particles trigger the generation of secondary emission electrons from a cathode. These generated electrons are subsequently amplified in a manner similar to the process within photomultiplier tubes. This report provides an insight into the principles underlying secondary emission calorimetry, presents findings from beam tests, and outlines Monte Carlo simulations that project towards the potential application of large-scale secondary emission electromagnetic calorimeters. © 2022 IEEE.
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    Study on gamma radiation attenuation and non-ionizing shielding effectiveness of niobium-reinforced novel polymer composite
    (Korean Nuclear Soc, 2022) Akman, Ferdi; Ogul, H.; Ozkan, I; Kacal, M. R.; Agar, O.; Polat, H.; Dilsiz, K.
    Advanced radiation applications have been widely used and extended to many fields. As a result of this fact, choosing an appropriate shielding material based on the radiation application has become vital. In this regard, the integration of elements into polymer composites has been investigated and contributed to the quantity and quality of radiation shielding materials. This study reports photon attenuation parameters and electromagnetic shielding effectiveness of a novel polymer composite prepared with a matrix reinforced with three different proportions (5,10, and 15 wt%) of niobium content. Addition of Nb dopant improves both photon attenuation and electromagnetic shielding effectiveness for the investigated composites. Therefore, Nb(15%) polymer composite with highest concentration has been found to be the best absorber for ionizing and non-ionizing radiations. Consequently, the performed analyzes provide evidences that the prepared Nb-reinforced polymer composite could be effectively used as photon radiation attenuator and electromagnetic shielding material. (c) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
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    Utilization of Secondary Electron Emission Principle in Calorimeter Active Media
    (E D P Sciences, 2025) Bilki, B.; Dilsiz, K.; Ogul, H.; Onel, Y.; Sahbaz, K. K.; Southwick, D.; Tiras, E.
    Secondary electron emission is the primary signal formation and/or amplification technique utilized in accelerator beam monitors and photomultiplier tubes where incident energetic particles cause ejection of additional electrons from a secondary emission surface. The materials employed as surfaces for secondary electron emission have demonstrated exceptional resistance to radiation, making them suitable for serving as the active media in radiation-hard calorimeters. With this motivation, we developed dedicated secondary electron emission sensor modules, tested them with particle beams and developed Monte Carlo simulations to predict the performance of large-scale calorimeters. Here, the details of the sensor modules and the results of the beam tests and simulations will be discussed. Recently, we have applied high secondary emission yield materials, Al2O3 and TiO2, as surface coatings on the anode plates of one-glass resistive plate chambers developing the so-called hybrid resistive plate chambers. The beam test results manifestly show the contribution of the secondary emission layer on the overall electron multiplication in the gas gap. The measurements also enable preliminary assessment of the secondary emission principle in thin Al2O3 and TiO2 layers in a particle shower/avalanche environment and the development of Monte Carlo simulations. Here we describe the details of the direct utilization of the secondary electron emission surfaces and the impact of the findings on future implementations.