Yazar "Ugur, F. A." seçeneğine göre listele

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    Investigation of cross sections of reactions used in neutron activation analysis
    (Carl Hanser Verlag, 2011) Tel, E.; Sahan, M.; Ugur, F. A.; Sahan, H.; Aydin, A.
    In this study, neutron incident reaction cross sections for some target nuclei such as Mg-24, Al-27, Si-28, Fe-56, and Cu-63 used in neutron activation analysis have been investigated. The new calculations on the excitation functions of Mg-24(n, p)Na-24, Al-27(n, p)Mg-27, Al-27(n, alpha)Na-24, Si-28(n, p)Al-28, Fe-56(n, p)Mn-56, and Cu-63(n,2n)Cu-62 reactions have been carried out for incident neutron energies up to 20 MeV. In these calculations, the pre-equilibrium and equilibrium effects have been investigated. The pre-equilibrium calculations involve the new geometry dependent hybrid model and the full exciton model. Equilibrium effects are calculated according to the Weisskopf-Ewing model. In the present work, reaction cross-sections have been calculated by using empirical formulas developed for energies of 14-15 MeV. The calculated results are discussed and compared with the experimental data taken from the EXFOR database.
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    Investigation of Some Structural Fusion Materials for (n, alpha) Reactions at the 14-15 MeV Energy Region
    (Springer, 2011) Tel, E.; Sahan, M.; Aydin, A.; Bolukdemir, M.; Sahan, H.; Ugur, F. A.
    In fusion reactor structures, a serious damage mechanism has been gas production in the metallic resulting from diverse nuclear reactions, mainly through (n, alpha) and (n, p) reactions above a certain threshold energy. The neutron incident energy around 14-15 MeV is enough to excite the nucleus for the reactions such as (n, p), (n, d), (n, 2n), (n, t), and (n, alpha). Design of the fusion reactor, about the 14-15 MeV neutron incident energy reaction cross sections is of great importance for various target nuclei. In this study, the experimental data have been taken only at 14-15 MeV energy regions from EXFOR database. The (n, alpha) reactions for some structural fusion materials such as Al-27, V-51, Cr-52, Mn-55, Fe-56 and Ni-58 have calculated by using evaluated empirical formulas developed by Tel et al. at 14-15 MeV and calculated with the pre-equilibrium models up to 20 MeV. The calculated results are discussed and compared with the experimental data taken from EXFOR database.
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    The Study of (n,d) Reaction Cross Sections for Some Medium Weight Targets up to 30 MeV
    (Springer, 2011) Aydin, A.; Sahan, M.; Tel, E.; Sahan, H.; Ugur, F. A.
    In this study, neutron incident reaction cross sections for some medium target nuclei ( (44) Ca, (65) Cu, (54) Fe, (56) Fe, (57) Fe, (58) Ni, (60) Ni and (67) Zn) have been investigated for the (n,d) reaction cross sections. These new calculations on the excitation functions of (44) Ca(n,d) (43) K, (65) Cu(n,d) (44) Ni, (54) Fe(n,d) (53) Mn, (56) Fe(n,d) (55) Mn, (57) Fe(n,d) (56) Mn, (58) Ni(n,d) (57) Co, (60) Ni(n,d) (59) Co and (67) Zn(n,d) (66) Cu reactions have been carried out up to 30 MeV incident neutron energy. In these calculations, the pre-equilibrium and equilibrium effects have been investigated. The PEQ calculations involve the new evaluated the Geometry Dependent Hybrid model. Equilibrium effects are calculated according to the Weisskopf-Ewing model. By using the new cross sections formulae for (n,d) reactions developed by Aydin et al., the obtained results have been discussed and compared with the available experimental data taken from EXFOR database.
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    A Study on Be8-18 Isotopes Used on Neutron Multiplier in Reactor Design
    (Springer, 2011) Tel, E.; Akti, N. N.; Okuducu, S.; Aydin, A.; Sahan, M.; Ugur, F. A.; Sahan, H.
    Neutronic characterization and development of structural materials, neutron multiplier materials, tritium breeders are primarily important for fusion and hybrid reactors. In order to improve neutron economy, beryllium, lead, bismuth, zirconium are considered and used as neutron multiplier materials in fusion and hybrid reactor design. In this study, rms charge radii, neutron radii, mass radii and neutron skin thickness were calculated for Be8-18 isotopes nuclei. The neutron and proton density are calculated for Be isotopes. The results obtained were compared with the experimental and theoretical results of other researchers by using Hartree-Fock method with an effective interaction with Skyrme forces.