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Öğe A study on the criticality of modified neutron transport equation by using alternative scattering phase functions(Carl Hanser Verlag, 2015) Kara, A.; Anli, F.PN approximation is known as a proper method to solve neutron transport equation when literature is taken into consideration. Generally, conventional scattering function is used to solve criticality and diffusion problems in Legendre polynomial approximation. In this study, instead of conventional scattering function, Henyey-Greenstein (HG) and Anli-Gungor phase functions (AG) are used in slab geometry transport equation and some critical thicknesses of the slab are calculated as an application with Legendre polynomial (PN) approximation and Marshak boundary condition. Results obtained from HG and AG scattering functions are compared and the correlations and discrepancies between the two functions are presented in the tables.Öğe Calculations of Double-Differential Neutron Emission Cross Sections for 9Be Target Nucleus at 14.2 MeV Neutron Energy(Springer, 2015) Sahan, M.; Tel, E.; Sahan, H.; Kara, A.; Aydin, A.; Kaplan, A.; Sarpun, I. H.In this study, we investigated neutron-emission spectra induced by (n,xn) nuclear reactions for the Be-9 structural fusion material at 14.2 MeV neutron energy. We calculated double-differential cross sections () with ALICE-2011 codeor the angles of 30A degrees, 60A degrees, 90A degrees, 120A degrees, and 150A degrees. Hybrid Monte Carlo simulation model have been used to calculate the double differential emission spectra for these different angles. The obtained results were compared with the measured data taken from EXFOR library. The results show an acceptable agreement.Öğe Cross Section Calculations of (n,2n) and (n,p) Nuclear Reactions on Germanium Isotopes at 14-15 MeV(Springer, 2016) Sahan, M.; Tel, E.; Sahan, H.; Gevher, U.; Kara, A.Neutron incident reaction cross sections of Germanium isotopes (Ge-70,Ge-72,Ge-74,Ge-76) were investigated for the (n,2n) and (n,p) reactions around 14-15 MeV. Cross section calculations have been presented for Ge-70(n,2n)Ge-69, Ge-72(n,2n)Ge-71, Ge-74(n,2n)Ge-73, Ge-76(n,2n)Ge-75, Ge-70(n,p)Ga-70, Ge-72(n,p)Ga-72, Ge-74(n,p)Ga-74, and Ge-76(n,p)Ga-76 reactions. Theoretical calculations were performed with four different computer codes: ALICE/ASH for the Geometry Dependent Hybrid model, TALYS 1.6 for two component Exciton model, EMPIRE 3.2 Malta for Exciton model and PCROSS for Full Exciton model with the incident neutron energy up to 20 MeV. The (n,2n) and (n,p) reaction cross section calculations were compared with empirical formulas derived by several researchers and compared with the experimental data obtained from EXFOR database as well as with evaluated Nuclear data files (ENDF/B-VII.1: USA 2014). Results show good agreement between the theoretical calculations having a major importance in nuclear data evaluation calculations and the experimental data from literature.Öğe Effect of ultra high temperature ceramics as fuel cladding materials on the nuclear reactor performance by SERPENT Monte Carlo code(Carl Hanser Verlag, 2016) Korkut, T.; Kara, A.; Korkut, H.Ultra High Temperature Ceramics (UHTCs) have low density and high melting point. So they are useful materials in the nuclear industry especially reactor core design. Three UHTCs (silicon carbide, vanadium carbide, and zirconium carbide) were evaluated as the nuclear fuel cladding materials. The SERPENT Monte Carlo code was used to model CANDU, PWR, and VVER type reactor core and to calculate burnup parameters. Some changes were observed at the same burnup and neutronic parameters (keff, neutron flux, absorption rate, and fission rate, depletion of U-238, U-238, Xe-135, Sm-149) with the use of these UHTCs. Results were compared to conventional cladding material zircalloy.Öğe Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine(Walter De Gruyter Gmbh, 2015) Kara, A.; Korkut, T.; Yigit, M.; Tel, E.Radiopharmaceuticals are radioactive drugs used for diagnosis or treatment in a tracer quantity with no pharmacological action. The production of radiopharmaceuticals is carried out in the special research centers generally using by the cyclotron systems. Indium-111 is one of the most useful radioisotopes used in nuclear medicine. In this paper, we calculated the production cross sections of In-111 radioisotope via Cd111-114(p,xn) nuclear reactions up to 60 MeV energy. In the model calculations, ALICE/ASH, TALYS 1.6 and EMPIRE 3.2 Malta nuclear reaction code systems were used. The model calculation results were compared to the experimental literature data and TENDL-2014 (TALYS-based) data.
