Yazar "Korkmaz, Mehmet Emin" seçeneğine göre listele

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    Burnup calculations using serpent code in accelerator driven thorium reactors
    (Carl Hanser Verlag, 2013) Korkmaz, Mehmet Emin; Yi?it, Mustafa; A?ar, Osman
    In this study, burnup calculations have been performed for a sodium cooled Accelerator Driven Thorium Reactor (ADTR) using the Serpent 1.1.16 Monte Carlo code. The ADTR has been designed for burning minor actinides, mixed Th-232 and mixed U-233 fuels. A solid Pb-Bi spallation target in the center of the core is used and sodium as coolant. The system is designed for a heating power of 2 000 MW and for an operation time of 600 days. For burnup calculations the Advanced Matrix Exponential Method CRAM (Chebyshev Rational Approximation Method) and different nuclear data libraries (ENDF7, JEF2.2, JEFF3.1.1) were used. The effective multiplication factor change from 0.93 to 0.97 for different nuclear data libraries during the reactor operation period.
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    Excitation functions of neutron induced nuclear reactions for CO-59 nucleus using different level density models
    (Polish Acad Sciences Inst Physics, 2017) Korkmaz, Mehmet Emin; Yiğit, Mustafa; Ağar, Osman
    Cobalt alloys have been used in nuclear reactor design because these alloys have favourable mechanical properties at high temperatures. In this work, the nuclear cross section data of Co-59(n, 2n) Co-58, Co-59(n, 3n) Co-57, Co-59(n, 4n) Co-56, Co-59(n, np) Fe-58, Co-59(n, t) Fe-57, Co-59(n, He-3) Mn-57 and Co-59(n, 2n alpha) Mn-54 reactions were obtained by using TALYS 1.8 and ALICE/ASH codes. Effects on the cross section data of nuclear level density models in the calculations were investigated. In addition, the obtained results of the cross section calculations are discussed and compared with the measured values from the literature.
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    Investigation of spherical and cylindrical catural Iridium targets by photonuclear reaction
    (E D P Sciences, 2017) Korkmaz, Mehmet Emin; Ağar, Osman; Yiğit, Mustafa; Aydın, A; Sarpun, IH; Tel, E; Kaplan, A; Demir, B
    In this study, natural iridium consisting of Ir-191 and Ir-193 isotopes has been irradiated with 21 MeV photons. The distribution of photons, electrons and neutrons fluxes in the spherical and cylindrical natural iridium target have been calculated using MCNPX 2.7.0 Monte Carlo code. The intensity of the photon fluxes on both targets has been compared to the 10(6) particle story by showing them as mesh and optimizing the two targets.
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    On the behavior of cross-sections of charged particle-induced reactions of Ta-181 target
    (WORLD SCIENTIFIC PUBL CO PTE, 2018) Yi?it, Mustafa; Korkmaz, Mehmet Emin
    The production of nuclear energy from fusion reaction with no CO2 emission is one of the most attractive sources for the future. The unprecedented physical and mechanical properties for structural materials are very important in the nuclear fusion reactor design. So, tantalum material is a valuable candidate for plasma-facing materials in the fusion devices. In this paper, nuclear excitation functions for the Ta-181(p, n) W-181, Ta-181(p, 2n) W-180, Ta-181(p, 4n) W-178, Ta-181(d, 2n) W-181, Ta-181(a, n) Re-184 and Ta-181(a, 2n) Re-183 reactions are obtained using the nuclear codes TALYS 1.8 and ALICE/ASH. The contribution of pre-equilibrium and equilibrium processes in these reactions is investigated. In the calculations, the Weisskopf-Ewing and Hauser-Feshbach formalisms for the equilibrium particle emission, and the two-component exciton, hybrid and geometry-dependent hybrid formalisms for the pre-equilibrium particle emission are used. Hence, the cross-sections calculated are compared with the measured values. It is observed that the cross-section results of the geometry-dependent hybrid model match fairly well with the experimental measurements.