Yazar "Sarpun, I. H." seçeneğine göre listele

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    (3He,xn) Reaction Cross-Section Calculations for the StructuralFusion Material 181Ta in the Energy Range of 14–75 MeV
    (Springer, 2014) Kaplan, A.; Capali, V.; Ozdogan, H.; Aydin, A.; Tel, E.; Sarpun, I. H.
    The theoretical neutron-production cross-sections produced by Ta-181(He-3,xn)Re184-x reactions (x = 1-7) for structural fusion material Ta-181 in He-3-induced reactions have been performed in the incident He-3 energy range of 14-75 MeV. Reaction cross-sections, based on theoretical pre-equilibrium nuclear reaction models, have been calculated theoretically by means of the TALYS 1.6 two component exciton, EMPIRE 3.1 exciton, ALICE/ASH geometry dependent hybrid (GDH) and ALICE/ASH hybrid models. The neutron-production cross-section results of the models have been compared with the each other and against the experimental nuclear reaction data (EXFOR). Except the Ta-181(He-3,2n)Re-182 and Ta-181(He-3,7n)Re-177 reactions, the ALICE/ASH cross-section calculations show generally agreement with the experimental values for all reactions used in this study. The ALICE/ASH-GDH model can be suggested, if the experimental data are unavailable or are improbably to be produced because of the experimental troubles.
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    Calculations of Double Differential Deuteron Emission Cross Sections at 62 MeV Proton Induced Reactions
    (Springer, 2013) Aydin, A.; Sarpun, I. H.; Kaplan, A.; Tel, E.
    In this study, double differential deuteron emission cross sections for Al-27, Fe-54,Fe-56, Au-197, Pb-208 and Bi-209 target nuclei have been calculated by the TALYS code at 62 MeV proton energy. The use of TALYS involved calculations by the pre-equilibrium exciton model and the Hauser-Feshbach model. The calculated double differential cross sections have been compared with the experimental data taken from the literature.
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    Calculations of double-differential triton emission cross sections at 62-MeV proton-induced reactions
    (Pleiades Publishing Inc, 2014) Aydin, A.; Sarpun, I. H.; Kaplan, A.
    Double-differential cross sections (d (2) sigma/d Omega dE >) have been calculated and analyzed for triton production in proton-induced reactions on Al-27, Fe-54,Fe-56, Au-197, and Pb-208 target nuclei at incident energy of 62 MeV. Calculations of double-differential cross sections have been performed using nuclear models implemented in the TALYS 1.2 code. The calculated results of the double-differential cross sections for triton emission have been compared with the existing experimental data.
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    Comparison of Level Density Models for the Ni-60,Ni-61,Ni-62,Ni-64(p, n) Reactions of Structural Fusion Material Nickel from Threshold to 30 MeV
    (Springer, 2015) Aydin, A.; Pekdogan, H.; Kaplan, A.; Sarpun, I. H.; Tel, E.; Demir, B.
    The knowledge of level density for reaction cross-section calculations are needed for various applications such as fission and fusion reactor design, accelerator driven sub-critical systems, nuclear medicine, neutron capture and astrophysics. In this study, the excitation functions for (p, n) reactions from reaction threshold to 30 MeV proton incident energy on Ni-60, Ni-61, Ni-62 and Ni-64 isotopes were calculated using TALYS 1.6 nuclear code involving the level density models. This is of importance to the validation of nuclear model approaches with increased predictive power. There are several models of level density that can be used to predict cross-section. In this work, the (p, n) cross-sections would be calculated using three different model of level density, such as constant temperature model, back-shifted fermi gas model and generalized superfluid model on Ni-60,Ni-61,Ni-62,Ni-64 reactions. The (p, n) reaction cross-section calculations for Ni-60,Ni-61,Ni-62,Ni-64 target nuclei were compared with each other and the experimental nuclear reaction data obtained from EXFOR database.
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    Double Differential Cross Section and Stopping Power Calculations of Light Charged Particle Emission for the Structural Fusion Materials Cr-50,Cr-52
    (Springer, 2015) Demir, B.; Sarpun, I. H.; Kaplan, A.; Capali, V.; Aydin, A.; Tel, E.
    Double differential cross section is a fundamental value to determine nuclear heating and material damages in structural fusion material research. In this study, double differential light charged particle emission cross sections for Cr-50,Cr-52 target nuclei have been calculated by the TALYS 1.6 code at 14.8 MeV incident neutron energy. Penetrating distance and stopping powers have been calculated for the alpha, deuteron and proton particles, taking into consideration all possible reactions in Cr-50,Cr-52 for incident energies of 0.5-22.2 MeV using GEANT4 calculation code. The compound nucleus formation process dominates the emission of proton and alpha particles. Direct reaction contribution becomes dominant in higher particle emission energies. The calculated double differential cross sections have been compared with the available experimental data taken from the literature.
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    The Effect of the Deformation Parameter on the Cross Sections for Reactions: Pd-110(d,n)Ag-111 and Pd-110(d, 2n)(110m) Ag
    (Maik Nauka/Interperiodica/Springer, 2018) Boyukata, M.; Sarpun, I. H.; Aydin, A.
    In this study, we focused on the effects of the deformation parameter on the cross sections. First, the deformation parameters of target nucleus Pd-110 was determined within the interacting boson model (IBM). Later this parameter was used in the TALYS-1.8 code to calculate the cross sections of the Pd-110(d,n)Ag-111 and Pd-110(d, 2n)(110m) Ag reactions. Moreover, other deformation parameters obtained RIPL-3 and TALYS default were used for the cross section calculation. The calculated results were compared with the experimental nuclear reaction data from EXFOR.
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    Excitation Functions Calculations of the Charged Particle-Induced Nuclear Reactions on the Be-9 Target
    (Springer, 2017) Tel, E.; Gok, A. A.; Sahan, M.; Sarpun, I. H.; Kavun, Y.; Aydin, A.
    In this study, calculation of charged particles induced nuclear reactions of beryllium (Be-9) target nuclei have been investigated in the incident proton and alpha at energy range from threshold to 50 MeV. The excitation functions for Be-9 target nuclei reactions have been calculated by using PCROSS nuclear reaction calculation code. Weisskopf-Ewing model for equilibrium, calculations and the full exciton and cascade exciton models for pre-equilibrium calculations were used. Also, the semi-empirical calculations for (p,alpha) reactions have been done by using cross section formula updated with new coefficient developed by Tel et al. (Pramana Indian Acad Sci 74(6):931, 2010). The calculated results were compared with the experimental data for different energy levels ranging from 0.00 to 9.65 MeV taken from the literature.
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    Level density parameter dependence of the fission cross sections of some subactinide nuclei induced by protons with the incident energy up to 250 MeV
    (Pergamon-Elsevier Science Ltd, 2009) Aydin, A.; Yalim, H. A.; Tel, E.; Sarer, B.; Unal, R.; Sarpun, I. H.; Dag, M.
    This study aims to show the dependence on the choice of the ratio of the level density parameters a(f) and a(n) corresponding to the saddle point of fission and equilibrium deformation of nucleus, respectively, of the proton induced fission cross sections of some subactinide targets. The method was employed using different level density parameter ratios for each fission cross section calculation in ALICE/ASH computer code. The ALICE/ASH code calculations were compared both with the available experimental data and with the Prokofiev systematics data. It is found that the fission cross sections dependent heavily on the choice of level density parameter ratio in the fission and neutron emission channels, a(f)/a(n), for some subactinide nuclei. To get a good description of the measured fission cross sections for subactinide nuclei, we used a ratio of the level density parameters in the fission and neutron emission channels. a(f)/a(n), depending both on the target-nucleus and on the energy of the projectile, in agreement with results published in literature. (C) 2009 Elsevier Ltd. All rights reserved.
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    Neutron Production Cross-Section and Geant4 Calculations of the Structural Fusion Material Co-59 for (alpha,xn) and (gamma,xn) Reactions
    (Springer, 2015) Demir, B.; Kaplan, A.; Capali, V.; Ozdogan, H.; Sarpun, I. H.; Aydin, A.; Tel, E.
    Recent advances in technology and computer sciences give us simplicity to investigate phenomena of nuclear physics. Scientists have improved various nuclear reaction codes such as Talys, Alice/ASH, Cem95, Empire, Geant4 and Fluka. These programs give us chance to calculate crucial quantity like reaction cross-section, energy spectrum of out-going particles, stopping power and penetrating distances in target material. The stopping power of alpha in Co-59 material is acquired as it has helpful applications of shielding and choosing the proper thickness of the target. Evaluation of the reaction cross-section data is very important to various applications such as improvement structural material, reactor design and radioisotopes production. In this study, we calculated the neutron production cross-sections of Co-59 using TALYS 1.6 and EMPIRE 3.1 codes for different level density models. Penetrating distances and stopping powers have been calculated for the alpha particles taking into consideration all possible reactions in Co-59 using GEANT4 simulation program. The obtained (alpha,xn) and (gamma,xn) reactions (x = 1, 2, 3) cross-section values have been compared with the each other and against the experimental nuclear reaction data existing in EXFOR database.
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    (γ, 2n)-Reaction cross-section calculations of several even-even lanthanide nuclei using different level density models
    (Maik Nauka/Interperiodica/Springer, 2015) Kaplan, A.; Sarpun, I. H.; Aydin, A.; Tel, E.; Capali, V.; Ozdogan, H.
    There are several level densitymodels that can be used to predict photo-neutron cross sections. Some of them are Constant Temperature + Fermi GasModel (CTFGM), Back-Shifted Fermi GasModel (BSFM), Generalized Superfluid Model (GSM), Hartree-Fock-Bogoliubov microscopic Model (HFBM). In this study, the theoretical photo-neutron cross sections produced by (gamma, 2n) reactions for several even-even lanthanide nuclei such as Ce-140,Ce-142, Nd-142,Nd-144,Nd-146,Nd-148,Nd-150, Sm-144,Sm-148,Sm-150,Sm-152,Sm-154, and Gd-160 have been calculated on the different level density models as mentioned above by using TALYS 1.6 and EMPIRE 3.1 computer codes for incident photon energies up to 30 MeV. The obtained results have been compared with each other and available experimental data existing in the EXFOR database. Generally, at least one level density model cross-section calculations are in agreement with the experimental results for all reactions except Sm-144(gamma, 2n) Sm-142 along the incident photon energy, TALYS 1.6 BSFM option for the level density model cross-section calculations can be chosen if the experimental data are not available or are improbable to be produced due to the experimental difficulty.