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Öğe 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.Öğe 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.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.Öğe 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.
