Yazar "Korkut, H." seçeneğine göre listele

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    Calculation of Particle Emissions and Fusion Cross Sections After 8B(t,*), 9B(t,*), and 10B(t,*) Reactions by Monte Carlo Simulations
    (Taylor & Francis Inc, 2020) Korkut, H.; Korkut, T.
    Boron nuclide and tritium projectile interactions are considerable in terms of nuclear energy systems. This study aims to investigate the realization of the nuclear fusion reactions of the bombardment of boron nuclei with tritium. In addition, the B-8(t,*), B-9(t,*), and B-10(t,*) reactions have focused on the use of the resulting product particles in nuclear technology applications, particularly in nuclear medicine applications, in terms of energy and number. Tritium-induced reactions from boron isotopes (B-8, B-9, and B-10) at 50 and 100 MeV were modeled by the GEANT4 and EMPIRE Monte Carlo codes. Gamma, alpha, tritium, deuteron, proton, and neutron emission spectra (GEANT4-10.3) were obtained, and cross sections per energy (EMPIRE-3.2-MALTA) were calculated. Fusion cross sections and Li-6 and Li-7 production cross sections, which are critical in thermonuclear fusion reactors as basic fusion reactions, are discussed based on the B-8(t,*), B-9(t,*), and B-10(t,*) reactions.
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    Öğe
    Effect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code
    (Carl Hanser Verlag, 2016) Korkut, T.; Kara, A.; Korkut, H.
    Ultra High Temperature Ceramics (UHTCs) have low density and high melting point. So they are useful materials in the nuclear industry especially reactor core design. Three UHTCs (silicon carbide, vanadium carbide, and zirconium carbide) were evaluated as the nuclear fuel cladding materials. The SERPENT Monte Carlo code was used to model CANDU, PWR, and VVER type reactor core and to calculate burnup parameters. Some changes were observed at the same burnup and neutronic parameters (keff, neutron flux, absorption rate, and fission rate, depletion of U-238, U-238, Xe-135, Sm-149) with the use of these UHTCs. Results were compared to conventional cladding material zircalloy.
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    Öğe
    Investigation of Dose Effect of ICRP110 Male and Female Head Phantoms During BNCT and PBFT by Monte Carlo Simulations
    (Natl Atomic Energy Agency Indonesia, 2025) Korkut, H.; Korkut, T.; Singh, V. P.
    Boron Neutron Capture Therapy (BNCT) and Proton Boron Fusion Therapy (PBFT) are of great interest in the field of radiation oncology. These treatment methods may offer different advantages and disadvantages depending on the type of tissue involved, as well as the location and size of the cancerous area. In this study, radiation dose effect of BNCT and PBFT on the brain, one of the most sensitive organs of the human body, was examined comparatively, based on the ICRP110 male and female head phantom models by using GEANT4 Monte Carlo simulations. Additionally, some necessary LET (Linear Energy Transfer) calculations are also presented in the article. Dose, LET and Energy deposition values of GEANT4 calculations were presented for BNCT and PBFT therapies in details for male and female phanthom comparatively. (c) 2025 Atom Indonesia. All rights reserved