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  1. Ana Sayfa
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Yazar "Kilicoglu, O." seçeneğine göre listele

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  • [ X ]
    Öğe
    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.
  • [ X ]
    Öğe
    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.
  • [ X ]
    Öğe
    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.
  • [ X ]
    Öğe
    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.
  • [ X ]
    Öğe
    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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