Yazar "Yavuzkanat, Nuray" seçeneğine göre listele

Listeleniyor 1 - 3 / 3
  • Küçük Resim
    Öğe
    Analyzing neutron and gamma ray shielding properties in varied W-B2O3 ratios: methodological comparisons and Monte Carlo simulation
    (Taylor & Francis Ltd, 2024) Yavuzkanat, Nuray; Sahmaran, Turan
    This study aims to comprehensively assess the radiation shielding efficacy of W-B2O3 composite material across varying ratios, contrasting its performance with glass and established literature data. The investigation involves comparing the radiation shielding capabilities of these materials using Geant4-based GATE simulation, XCOM, and EpiXS programs across energy levels ranging from 0.3-2.516 MeV. The research involved calculating and comparing the effective removal cross-section values of these materials with those commonly employed in neutron shielding. The findings indicate superior radiation shielding capabilities in the composite material compared to glass. Moreover, the mass attenuation coefficients were derived through GATE simulation at energy levels of 6 and 18 MV mono and spectrum energy. These values were then compared with theoretical methods; XCOM, XMuDat, and an innovative methodology outlined in the current literature. In the new approach, the effective atomic numbers of the materials were determined using the mass attenuation coefficients.
  • Küçük Resim
    Öğe
    Chemical and physical analysis of synthesized coumarin compounds: Investigating responses to gamma and neutron radiations
    (Pergamon-Elsevier Science Ltd, 2024) Yavuzkanat, Nuray; Sahmaran, Turan; Sarac, Kamuran
    This research investigates the chemical and physical characteristics of three recently synthesized coumarin compounds produced via the von Pechmann condensation mechanism. These compounds were successfully and precisely synthesized, as confirmed by a comprehensive understanding of their chemical composition obtained through combined infrared and NMR analyses. The compounds underwent examination regarding their responses to gamma and neutron radiations, and their mass attenuation coefficients (MAC) were determined using both GATE/Geant4 simulation and NIST-XCOM data. Additionally, the effective removal cross-section values for fast neutrons were calculated employing various methods. All acquired data has been compared with that of water and other materials in the existing literature. Although coumarin compounds might not have intrinsic shielding properties, they have the potential to be part of composite materials designed for specific applications. Comparative analysis with established radiation dosimetry systems showed the coumarin compounds' attenuation coefficients closely aligning with water, indicating their potential suitability for nuclear applications requiring water -equivalent properties. Further assessment with Geant4 simulation under linac photon beams demonstrated the water -equivalent properties of the coumarin compounds for 6 MV and 18 MV.
  • Küçük Resim
    Öğe
    Evaluation of gamma and neutron radiation shielding parameters of some glass materials by monte corlo and theoretical method
    (Taylor & Francis Ltd, 2024) Sahmaran, Turan; Yavuzkanat, Nuray
    The present study investigates the gamma-ray and neutron shielding properties of PbCu3Ti4O12, lithium borate (Li2B4O7), lithium borate glasses doped with dolomite (CaMg(CO3)) and neodymium oxide (Nd2O3) to assess their effectiveness as shielding materials against ionizing radiation. The gamma-ray shielding properties, including the attenuation and absorption characteristics of the materials were examined and compared using Geant4-based GATE simulation, XCOM, and EpiXS in the photon energy range of 80-2000 keV. When the shielding properties of the available materials were compared, it was determined that Li2B4O7-Nd2O3, PbCu3Ti4O12, Li2B4O7-CaMg(CO3), and Li2B4O7 exhibited the best shielding properties, in order from most effective to least effective. The neutron shielding properties of these materials, including scattering, absorption, and moderation capabilities, were also determined using MRCsC, Phy-X/PSD and estimation sigma R/rho of elements. The results were then compared with the current literature. Li2B4O7, CaMg(CO3), and Nd2O3-doped lithium borate glass samples showed higher effective fast neutron removal cross-section values than water and concrete in all calculation methods. It shows that the investigated glass materials are better gamma and neutron beam absorbers and have the potential for use in gamma and neutron beam shielding applications.