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Öğe Atomistic nano-scale 3D simulations about effects of Cr percentage on the molecular dynamics parameters of Fe-9-12% Cr alloys at fusion reactor temperature conditions(Carl Hanser Verlag, 2014) Korkut, T.; Sen, S.9-12% Cr ferritic steel structures at atomic scale were modeled by LAMMPS (Large-scale Atomic/Molecular Massively Parallel Simulator) Molecular Dynamics package with high accuracy. Embedded-Atom Model (EAM) potential parameters were applied for Fe-Fe, Fe-Cr and Cr-Cr atomic interactions. Nuclear reactor temperature conditions were used in the simulations. Heat flux, kinetic energy, potential energy, total energy, pressures, and atomic displacements of Fe-Cr steels including 9%, 10%, 11%, and 12% Cr were given.Öğe 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.Öğe Comparison of mass attenuation coefficients of concretes using FLUKA, XCOM and experiment results(Edp Sciences S A, 2018) Singh, V. P.; Korkut, T.; Badiger, N. M.The mass attenuation coefficients of seven different types of normal and heavy concretes like ordinary, hematite-serpentine, ilmenite-limonite, basalt-magnetite, ilmenite, steel-scrap and steel-magnetite concretes has been simulated using FLUKA Monte Carlo code at high energies 1.5, 2, 3, 4, 5 and 6MeV. The mass attenuation coefficients and linear attenuation coefficient of the concretes were found dependent upon the chemical composition, density and gamma ray energy. FLUKA Monte Carlo code results were found in good agreement with experimental and theoretical XCOM data. Our investigations for high energy gammaray interaction validate the FLUKA Monte Carlo code for use where experimental gamma-ray interaction results are not available.Öğe Development of Al2O3-Bi2O3-B2o3 glasses for neutron shielding material(Trans Tech Publications Ltd, 2016) Tuscharoen, S.; Insiripong, S.; Korkut, T.; Kaewkhao, J.A glass system with chemical formula xB2O3:20Bi2O3:(100-x) Al2O3 (x = 55, 60, 65, 70, 75 and 80 mol%) was prepared by melt quenching technique and were investigated the physical and neutron shielding properties. The physical properties were investigated by density, molar volume and discussed with different Al2O3 contents. The neutron shielding property was investigated by Monte Carlo techniques (FLUKA and GEANT4 codes) and neutron equivalent dose rate measurements. As a result, neutron shielding capacity of glass samples decrease with increased Al2O3 content, so increased B2O3 content is a result of positive effects on neutron shielding. © 2016 Trans Tech Publications, Switzerland.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.Öğe Fabrication of Ni, Cr, W reinforced new high alloyed stainless steels for radiation shielding applications(Elsevier, 2019) Aygun, B.; Sakar, E.; Korkut, T.; Sayyed, M. I.; Karabulut, A.; Zaid, M. H. M.Stainless steel is commonly used in radiation applications for its high temperature resistance and fine mechanical properties. In this study, three types of high alloyed stainless-steel samples were produced. Before the production, GEANT4 Monte Carlo simulation toolkit was used to estimate the total fast neutron macroscopic cross sections and gamma mass attenuation coefficients. The hot-pressing process and the powder metallurgy method were applied. We tested samples' chemical and mechanical strength. Samples were exposed to both gamma rays and fast neutrons. The obtained simulation and experimental results for both neutron and gamma radiation are compatible. According to the simulation and experimental results, neutron shielding capacity of the new stainless-steel alloys is higher than the most commonly used 316LN stainless steel in nuclear applications. Among the prepared samples, SSA1 steel has the smallest half value layer at the all examined energies. All the prepared samples posses higher mass attenuation coefficient values and lower half value layer than 316LN steel. This indicates that the produced three new high alloyed stainless-steel samples have high gamma absorption capacity when compared to 316LN steel.Öğe Gamma-ray and neutron shielding efficiency of Pb-free gadolinium-based glasses(Springer Singapore Pte Ltd, 2016) Singh, V. P.; Badiger, N. M.; Kothan, S.; Kaewjaeng, S.; Korkut, T.; Kim, H. J.; Kaewkhao, J.The radiation shielding efficiency of material depends upon photon attenuation, exposure buildup factors and neutron removal capacity. A newly developed Pb-free gadolinium-based glasses in compositions (80-x) B2O3-10SiO(2)-10CaO-xGd(2)O(3) (where x = 15, 20, 25, 30 and 35 mol%) had completely been investigated for their shielding efficiency with Geant4 simulation for mass attenuation coefficients and neutron total macroscopic cross section and by calculating exposure buildup factors. The exposure buildup factors for photon energy from 0.015 to 15 MeV had been calculated up to 40 mean free paths using five factors geometric progression method. The mass attenuation coefficients of the Pb-free glasses were simulated for energies from 223 to 2614 keV and compared with the possible available experimental results. The neutron shielding efficiency of these glasses was discussed by calculating neutron total macroscopic cross section for energies from 1 eV to 14.1 MeV. Present investigations are found to be very useful for applications in nuclear engineering.Öğe Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine(Walter De Gruyter Gmbh, 2015) Kara, A.; Korkut, T.; Yigit, M.; Tel, E.Radiopharmaceuticals are radioactive drugs used for diagnosis or treatment in a tracer quantity with no pharmacological action. The production of radiopharmaceuticals is carried out in the special research centers generally using by the cyclotron systems. Indium-111 is one of the most useful radioisotopes used in nuclear medicine. In this paper, we calculated the production cross sections of In-111 radioisotope via Cd111-114(p,xn) nuclear reactions up to 60 MeV energy. In the model calculations, ALICE/ASH, TALYS 1.6 and EMPIRE 3.2 Malta nuclear reaction code systems were used. The model calculation results were compared to the experimental literature data and TENDL-2014 (TALYS-based) data.
