Yazar "Kacal, Mustafa Recep" seçeneğine göre listele

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    A study on the interaction parameters of charged and uncharged radiation types with some indoor plants
    (Pergamon-Elsevier Science Ltd, 2024) Caf, Ahmet; Akman, Ferdi; Ogul, Hasan; Kacal, Mustafa Recep
    This study investigates how gamma rays, neutrons, and electrons interact with five commonly found indoor plants: Spathiphyllum wallisii (SW), Ficus elastica (FE), Dieffenbachia camilla (DC), Schefflera arboricola (SA), and Ficus benjamina (FB). Utilizing experimental measurements (with HPGe detector), Monte Carlo simulations (GEANT4 and FLUKA), and theoretical calculations (ESTAR and WinXCOM), some radiation interaction parameters for gamma rays, fast neutrons, thermal neutrons, and electrons were determined. Secondary particle generation was also analyzed to provide a comprehensive assessment. The determined linear attenuation coefficients with the help of the WinXCOM are 0.1376, 0.1662, 0.1385, 0.1651 and 0.1698 cm(-1 )for SW, FE, DC, SA and FB, respectively. The calculated total macroscopic cross sections for indoor plants in the same sample order are 2.0290, 2.0350, 2.0285, 2.0363 and 2.0362 cm(-1). Among the investigated plants, FB exhibited the highest gamma ray interaction, while SA and FB showed superior interaction against fast neutrons compared to SW and DC. The findings reveal significant variations in interaction effectiveness and secondary radiation production across these plants, offering valuable insights for radiation safety and environmental health evaluations.
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    Evaluation of CdS doped polyester composites regarding gamma and neutron shielding properties
    (Pergamon-Elsevier Science Ltd, 2021) Dilsiz, Kamuran; Ogul, Hasan; Akman, Ferdi; Agar, Osman; Kacal, Mustafa Recep; Polat, Hasan; Dursun, Inan
    In this study, CdS doped polyester composites were produced at different weight ratios, and the impact of dopant amount on gamma and neutron shielding characteristics of a new composite material were further evaluated: the composite matrix was doped at 5%, 10%, 15% and 20% CdS weight ratios of the prepared composite. Then, the produced polyester materials have been characterized using a scanning electron microscope (SEM) and X-ray diffraction (XRD) patterns. Following the structure characterization, the prepared composites were tested using one gamma spectrometer system based HPGe detector with help of Na-22, Mn-54, Co-57, Co-60, Ba-133, Cs-137, Eu-152 and Am-241 radioactive point-isotropic sources in order to perform the evaluation in a wide energy range of gamma. The obtained results were compared to the results of Geant4 and WinXCOM simulation codes. On the last step of the presented work, the neutron removal cross sections of produced polyester composites were calculated using partial density of elements and their cross sections, and then, neutron shielding characteristics of the prepared samples were determined with help of Geant4 simulation toolkit. Both tested and simulated results of gamma shielding evaluation showed good agreement, and, for all considered photon energies, mass attenuation coefficient (mu/p) values of CdS (20%) were always found to be greater than the mu/p values of other samples (5%, 10%, 15%). The results for neutron shielding showed that neutron transmission was decreasing with the increase of CdS in the material. In short, having higher mu/p values and lower neutron transmission shows that increasing the amount of CdS in the sample causes the higher radiation shielding property for both gamma and neutron.
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    Evaluation of radiation shielding, secondary radiation, and radiation damage in boron carbide and chromium diboride reinforced polymer composites
    (Elsevier Science Sa, 2025) Ogul, Hasan; Akman, Ferdi; Ozdogan, Hasan; Kacal, Mustafa Recep; Tursucu, Ahmet; Polat, Hasan; Erkoyuncu, Ilhami
    The presented work studies the radiation shielding effectiveness of polymer-based composites reinforced with B4C and CrB2 for both gamma-ray and neutron protection. The incorporation of CrB2 was found to significantly enhance gamma-ray attenuation, with the BCCrB-50 formulation demonstrating the highest shielding efficiency. Neutron shielding performance was also improved, particularly at thermal and fast neutron energies, with the additives playing a key role in reducing neutron transmission. Total Ionizing Dose (TID) and Displacement Per Atom (DPA) analyses were performed to assess the composites' radiation resistance, revealing that the BCCrB composites effectively minimize radiation exposure. These results suggest that BCCrB composites are a promising, environmentally friendly alternative for radiation shielding in various applications, including nuclear energy systems.
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    Gamma and Neutron Interaction Characteristics of Hf-Reinforced CuAlNi Alloys: Experimental and Monte Carlo Evaluation
    (Taylor & Francis Inc, 2026) Niksarlioglu, Secil; Kacal, Mustafa Recep; Ogul, Hasan; Akman, Ferdi
    This study presents the gamma and neutron radiation shielding efficiency of CuAlNi alloys reinforced with different weight percentages (3 wt%, 6 wt%, and 9 wt%) of Hf, the secondary radiations generated due to the radiation interaction with the produced alloys, and the Total ionizing dose and displacement per atom parameters to determine the radiation effect on the considered alloys. CuAlNi-Hf alloys are promising because of their shape memory property. Experimental gamma radiation measurements were performed with a high-purity germanium detector using 241Am, 133Ba, 22Na, 137Cs, and 60Co radioactive sources, while Monte Carlo simulations and theoretical calculations were performed with the GEANT4, FLUKA, and WinXCOM programs.The gamma radiation shielding efficiency of the CuAlNi-based alloys increased with higher Hf content, whereas their thermal neutron shielding efficiency decreased. According to the obtained results of all the presented parameters, the CuAlNiHf9 alloy had the best gamma radiation shielding properties, while the CuAlNiHf0 alloy exhibited superior shielding properties at epithermal energies neutron (100 eV). The CuAlNiHf9 alloy, with mass attenuation coefficient values of 1.6136 cm2/g-1 at 59.5 keV, 0.0871 cm2/g-1 at 661.7 keV, and 0.0515 cm2/g-1 at 1332.5 keV, was identified as the alloy that provided the highest protection against gamma radiation. The total ionizing dose and displacement per atom values were observed to rise with increasing gamma-ray energy, while thermal and fast neutrons exhibited a nonlinear trend.
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    Gamma radiation shielding performance of CuxAg(1-x)-yalloys: Experimental, theoretical and simulation results
    (Pergamon-Elsevier Science Ltd, 2022) Turhan, Mehmet Fatih; Akman, Ferdi; Taser, Ahmet; Dilsiz, Kamuran; Ogul, Hasan; Kacal, Mustafa Recep; Agar, Osman
    Different types of photon shielding parameters such as total mass attenuation coefficient (mu/p), linear attenuation coefficients (mu), half value layers (HVL), mean free paths (MFP), effective atomic numbers (Z(Eff)), energy absorption build-up factors (EABF), exposure build-up factors (EBF) and kerma relative to air were investigated for the fabricated Cu-Ag based alloys. The considered parameters were measured through gamma spectrometer equipped with HPGe detector in order to obtain the experimental attenuation coefficients and other related parameters at various photon energy in the energy range 59.5-1332.5 keV. The measured mu/rho values were confirmed with WinXCOM database results. FLUKA and GEANT4 simulation codes were used to examine the compatibility of the experimental and WinXCOM database results with these simulation codes. The exposure buildup factors of the alloy samples were estimated with help of Geometric Progression fitting formula over photon energy 0.015-15 MeV up to 40 mfp penetration depth. The results revealed that the exhibited effectiveness of Cu0.2Ag0.8 alloys against high energetic photon radiations had a good performance than that of alternative absorbers such conventional concretes, glasses and some alloys. The results of the present survey can be quite useful for possible applications of such materials, especially in nuclear laboratory and reactor core design for preference of effective photon shielding materials.
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    Production and evaluation of the polyester composites containing pyrite and niobium diboride for radiation protection
    (Pergamon-Elsevier Science Ltd, 2025) Akman, Ferdi; Turhan, Mehmet Fatih; Ogul, Hasan; Tursucu, Ahmet; Erdogan, Taha; Kacal, Mustafa Recep; Polat, Hasan
    The presented study focused on investigating the radiation shielding properties of polyester/pyrite/niobium diboride (FeSNbB) composites. Various gamma-ray shielding parameters were evaluated with help of a HPGe detector system. Theoretical and simulation results are further evaluated by WinXCOM, GEANT4 and FLUKA codes, and the obtained results are compared with experimental values in the energy region 59.5 keV-1332.5 keV. The prepared samples are additionally evaluated using kerma relative to air values and Exposure build-up factors. Then, for the evaluation of neutron radiation shielding, effective removal cross sections for fast neutrons were determined for FeSNbB composites. Electron attenuation efficiency (AE%) for the produced composites was assessed across the energy spectrum of 4 MeV-18 MeV, utilizing experimental data from a Linac machine and theoretical predictions from Eclipse TPS. The results were found to be compatible with each other. FeSNbB50 has the best shielding properties among the studied composites.