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Öğe Calculation of cross-sections and astrophysical s-factors for the 63 Cu(α,n) and 63 Cu(α,γ) reactions(E D P Sciences, 2015) Yildiz, Ercan; Aydin, Abdullah; Sarpun, Ismail Hakki; Tel, EyyupThe cross sections and astrophysical S-factors of the Cu-63(alpha,gamma) and Cu-63(alpha,n) reactions have been calculated. The radiative alpha capture reaction cross sections was calculated in the incident energy range of 3 to 10 MeV and the (alpha,n) reaction cross sections was calculated in the incident energy range of 7 and 16 MeV. In these theoretical calculations, the TALYS 1.6 and NON-SMOKER codes were used. Also for these reactions, it was calculated the astrophysical S-factors which describe the possibility of reaction in low energies. Obtained results were compared to the experimental data taken from EXFOR database.Öğe Calculations of Cross-Sections and Astrophysical S-factors for the (alpha,n) Reactions of Some Structural Fusion Materials(Springer, 2017) Yildiz, Ercan; Aydin, Abdullah; Sarpun, Ismail Hakki; Tel, EyyupStructural material selection in design of fusion reactors is very crucial. These structural materials should satisfy the hard conditions such as high thermo-mechanical stresses, high heat loads and severe radiation damage without compromising on safety considerations. The materials such as titanium, vanadium and chromium are used in the construction of fusion reactors. Therefore, it is important to examine these materials. Obtained results from the nuclear reactions using structural materials can be used for developing of these structural materials. For this reason, in this study cross sections of the Ti-46(alpha,n) Cr-49, Cr-50(alpha,n) Fe-53 and V-51(alpha,n) Mn-54 reactions have been calculated at 2-20 MeV energy range. In these theoretical calculations, the TALYS 1.8 and NON-SMOKER codes were used. Also, the astrophysical S-factors which describe the possibility of reaction in low energies were calculated. Results of our calculations were checked to the experimental data obtained from EXFOR database.Öğe Determination of the effects of nuclear level density parameters on photofission cross sections of U-235 up to 20 MeV(E D P Sciences, 2017) Sarpun, Ismail Hakki; Aydin, Abdullah; Pekdogan, HakanThe level density models and level density parameters are two of important quantities for describing the properties of nuclei. Especially, the level density parameter has an important role as input in calculation of reaction cross sections. In this study, the cross sections on U-235(g,f) reaction were calculated for different level density models using the TALYS 1.6 code up to 20MeV gamma incident energies. First, it was determined the level density model that was the closest to the experimental data. Secondly, cross sections obtained for different level density parameters of this model were compared with experimental data from the EXFOR database. Thus it was determined the best level density parameter fit to experimental data.Öğe Determinations of fission cross-sections and fission yields from proton induced fission reactions of 232Th, 233,235,236,238U, 237Np and 239Pu(World Scientific Publ Co Pte Ltd, 2021) Sarpun, Ismail Hakki; Yalim, Huseyin Ali; Aydin, Abdullah; Tel, Eyyup; Akdeniz, Ferhan; Sahin, SelcanIn this work, the proton induced fission reaction cross-sections and fission yields are calculated for some actinides (Th-232, U-233,U-235,U-236,U-238, Np-237, and Pu-239) using the fission barrier models of the TALYS 1.95 code. Cross-sections and fission yield calculations are carried out up to 100 MeV incident proton energies. The calculation results are compared with the available experimental data in the EXFOR library. In addition, a relative variance analysis of fission barrier models was done to determine the fission barrier model whose results best matched with the experimental results. Among the fission barrier models, the best agreement with the experimental data is obtained from the rotating-finite-range fission barrier model calculation for the (p,f) reaction of the studied nuclei having the atomic mass number larger than 230. On the other hand, fission barrier heights for the studied reactions are determined using the same models.Öğe Double differential light charged particle emission cross sections for some structural fusion materials(E D P Sciences, 2017) Sarpun, Ismail Hakki; Aydin, Abdullah; Tel, EyyupIn fusion reactors, neutron induced radioactivity strongly depends on the irradiated material. So, a proper selection of structural materials will have been limited the radioactive inventory in a fusion reactor. First-wall and blanket components have high radioactivity concentration due to being the most flux-exposed structures. The main objective of fusion structural material research is the development and selection of materials for reactor components with good thermo-mechanical and physical properties, coupled with low-activation characteristics. Double differential light charged particle emission cross section, which is a fundamental data to determine nuclear heating and material damages in structural fusion material research, for some elements target nuclei have been calculated by the TALYS 1.8 nuclear reaction code at 14-15 MeV neutron incident energy and compared with available experimental data in EXFOR library. Direct, compound and pre-equilibrium reaction contribution have been theoretically calculated and dominant contribution have been determined for each emission of proton, deuteron and alpha particle.Öğe Investigation of Nucleon Mean Free Path Dependence in Tritium Emission Spectra Produced by Proton Induced Reactions at 62 MeV(Springer, 2010) Yalim, Hueseyin Ali; Aydin, Abdullah; Sarpun, Ismail Hakki; Unal, Ridvan; Oruncak, Bekir; Kaplan, Abdullah; Tel, EyyupThis study aims on the effect of nucleon mean free path on differential cross sections of tritium-emission spectra for (p, H-3) reactions on Al-27, Fe-54,Fe- 56, Y-89, Sn-120, Au-197, Pb-208 and Bi-209 induced by 62 MeV protons in the pre-equilibrium reaction mechanisms. The pre-equilibrium calculations were carried out by using the geometry dependent hybrid model. The calculated results are compared with experimental data existing in literature and found to be in good agreement. Furthermore, using different multiplication factor for the mean free path in the calculation changes the differential cross sections of tritium emission spectra.Öğe Investigation of the effects of nuclear level density parameters on the cross sections for the U-234(gamma,f) reaction(E D P Sciences, 2015) Pekdogan, Hakan; Aydin, Abdullah; Sarpun, Ismail HakkiIn this study, we have investigated the effects of nuclear level density parameters on the cross sections for the U-234(gamma,f) reaction up to 20 MeV. The cross sections on U-234(gamma,f) reaction were calculated for different level density models using the TALYS 1.6 code. First, it was determined the level density model that was the closest to the experimental data. Secondly, cross sections obtained for different level density parameters of this model were compared with experimental data from the EXFOR database. Thus it was determined the best level density parameter fit to experimental data.Öğe A study on nuclear properties of Zr, Nb, and Ta nuclei used as structural material in fusion reactor(E D P Sciences, 2015) Sahan, Halide; Tel, Eyyup; Sahan, Muhittin; Aydin, Abdullah; Sarpun, Ismail Hakki; Kara, Ayhan; Doner, MesutFusion has a practically limitless fuel supply and is attractive as an energy source. The main goal of fusion research is to construct and operate an energy generating system. Fusion researches also contains fusion structural materials used fusion reactors. Material issues are very important for development of fusion reactors. Therefore, a wide range of fusion structural materials have been considered for fusion energy applications. Zirconium (Zr), Niobium (Nb) and Tantalum (Ta) containing alloys are important structural materials for fusion reactors and many other fields. Naturally Zr includes the Zr-90 (%51.5), Zr-91 (%11.2), Zr-92 (%17.1), Zr-94 (%17.4), Zr-96 (%2.80) isotopes and Nb-93 and Ta-181 include the Nb-93 (%100) and Ta-181 (%99.98), respectively. In this study, the charge, mass, proton and neutron densities and the root-mean-square (rms) charge radii, rms nuclear mass radii, rms nuclear proton, and neutron radii have been calculated for Zr87-102, Nb-93,Ta-181 target nuclei isotopes by using the Hartree-Fock method with an effective Skyrme force with SKM*. The calculated results have been compared with those of the compiled experimental taken from Atomic Data and Nuclear Data Tables and theoretical values of other studies.Öğe Theoretical investigation of cross sections and astrophysical S-factors for the Mo-92(alpha,n)Ru-95 and Mo-94(alpha,n)(97) Ru reactions(E D P Sciences, 2016) Aydin, Abdullah; Yildiz, Ercan; Sarpun, Ismail HakkiMolybdenum is commonly applied as a constructive material in different types of nuclear reactors. The cross sections of the Mo-92(alpha, n) Ru-95 and Mo-94(alpha, n) Ru-97 reactions have been calculated at 5-20 MeV energy ranges. In theoretical calculations, the TALYS1.6 and NON-SMOKER codes were used. Also the astrophysical S-factors were calculated. Results of our calculations were checked to the experimental data obtained from EXFOR database.
