Yazar "Capali, V." 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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    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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    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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    Production cross-section calculations of medical P-32, Sn-117, Sm-153 and Re-186,Re-188 radionuclides used in bone pain palliation treatment
    (Carl Hanser Verlag, 2015) Demir, B.; Kaplan, A.; Capali, V.; Sarpun, I. . H.; Aydin, A.; Tel, E.
    In this study, production cross-section calculations of P-32, Sn-117, Sm-153 and Re-186,Re-188 radionuclides used in bone pain palliation treatment produced by Si-30(d,gamma)P-32, Sn-118(gamma,n)Sn-117, Sn-116(n,gamma)Sn-117, Nd-150(alpha,n)Sm-153, Sm-154(n,2n)Sm-153, Sm-152 (n,gamma)Sm-153, W-186(d,2n)Re-186, Re-187(gamma,n)Re-186, Re-185(n,gamma)Re-186 and Re-187(n,gamma)Re-188 reactions have been investigated in the different incident energy range of 0.003-34 MeV. Two-component exciton and generalised superfluid models of the TALYS 1.6 and exciton and generalised superfluid models of the EMPIRE 3.1 computer codes have been used to pre-equilibrium (PEQ) reaction calculations. The calculated production cross-section results have been compared with available experimental results existing in the experimental nuclear reaction database (EXFOR). Except the Sn-118(gamma,n)Sn-117, Nd-150 (alpha,n)Sm-153 and Re-185(n,gamma)Re-186 reactions, the two-component exciton model calculations of TALYS 1.6 code exhibit generally good agreement with the experimental measurements for all reactions used in this present study.
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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.