Yazar "Ozdogan, H." seçeneğine göre listele

Listeleniyor 1 - 6 / 6
  • Küçük Resim
    Öğe
    (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.
  • Küçük Resim
    Öğe
    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.
  • [ X ]
    Öğe
    Photo-neutron Cross Section Calculations of Several Structural Fusion Materials
    (Springer, 2013) Kaplan, A.; Ozdogan, H.; Aydin, A.; Tel, E.
    In this study, the theoretical photo-neutron cross-sections produced by (gamma,n) reactions for several structural fusion materials such as V-51, Mn-55, Ni-58, Zr-90,Zr-91,Zr-92,Zr-94, and Ta-181 have been investigated in the incident energy range of 7-40 MeV. Reaction cross-sections as a function of photon energy have been calculated theoretically using the PCROSS and TALYS 1.2 computer codes. TALYS 1.2 default and pre-equilibrium models have been used to calculate the pre-equilibrium photo-neutron cross-sections. For the reaction equilibrium component, PCROSS Weisskopf-Ewing model calculations have been preferred. The calculated results have been compared with each other and against the experimental data in the existing databases EXFOR and TENDL-2011. PCROSS Weisskopf-Ewing model calculations show a similar structure with experimental data but they are higher than the experimental values for all reactions except for Zr-90(gamma,n)Zr-89 reaction. Generally, TALYS 1.2 default and pre-equilibrium model cross-section calculations are the best agreement with the experimental data for all reactions except for Ni-58(gamma,n)Ni-57 reaction along the incident photon energy in this study. The TALYS 1.2 curves fit the TENDL-2011 data the best. If photo-neutron cross-section data is needed for an isotope where there is no experimental data available for comparison, TALYS 1.2 pre-equilibrium option has been recommended.
  • Küçük Resim
    Öğe
    Photo-neutron cross-section calculations of 142,143,144,145,146,150Nd rare-earth isotopes for (γ, n) reaction
    (Pleiades Publishing Inc, 2014) Kaplan, A.; Ozdogan, H.; Aydin, A.; Tel, E.
    The theoretical photo-neutron cross sections for (gamma, n) reaction have been calculated on 142,143,144,145,146,150Nd rare-earth isotopes at photon energies of 8-23 MeV using the PCROSS, TALYS 1.2, and EMPIRE 3.1 computer codes. TALYS 1.2 two-component exciton model and EMPIRE 3.1 exciton model has been used to calculate the pre-equilibrium photo-neutron cross sections. PCROSS Weisskopf-Ewing model has been used for the reaction equilibrium cross-section calculations. The obtained cross sections have been compared with each other and against the experimental values existing in the EXFOR database. Generally, pre-equilibrium model cross-section calculations are in good agreement with the experimental data for all reactions along the incident photon energy in this study.
  • Küçük Resim
    Öğe
    (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.
  • Küçük Resim
    Öğe
    (γ,2n) Reaction Cross Section Calculations on Several Structural Fusion Materials
    (Springer, 2013) Kaplan, A.; Ozdogan, H.; Aydin, A.; Tel, E.
    In this study, the theoretical photo-neutron cross-sections produced by (gamma,2n) reactions for several structural fusion materials such as V-51, Mn-55, Ni-58, Zr-90,Zr-91,Zr-92,Zr-94, and Ta-181 have been carried out for incident photon energies up to 40 MeV. Reaction cross-sections as a function of photon energy have been calculated theoretically using the PCROSS and TALYS 1.2 computer codes. TALYS 1.2 default and pre-equilibrium models have been used to calculate the pre-equilibrium photo-neutron cross-sections. For the reaction equilibrium component, PCROSS Weisskopf-Ewing model calculations have been preferred. The calculated results have been compared with each other and against the experimental data in the existing databases EXFOR. Generally, TALYS 1.2 default and pre-equilibrium model cross-section calculations are in good agreement with the experimental data for all reactions along the incident photon energy in this study. Pre-equilibrium option can be recommended, if experimental data are not available or are unlikely to be produced due to the experimental difficulty.