Calculations of differential cross section of inelastic neutron scattering in fourth period elements

Nuclear fusion can be one of the most important energy sources because of its safety and minimum effects on environment in future. Because fusion cannot produce CO2 and SO2, it will prevent global warming or environmental problems like acid rains. By interceding of fusion reactors, improving of hybrid reactors which connects fusion-fission reactions comes up. Furthermore, radioactive nucleus half-lives which are produced in reactors are generally short. For this reason, it is not possible to measure cross section of these nucleus directly. Therefore, cross section formulas of experimental and semi-experimental reaction are improved in order to estimate this cross section theoretically. In nuclear fusion reactors, neutron which are formed as a result of reaction can make up. Inelastic scattering reaction with various elements which are used as a reactor construction material. This study is conducted for the aim of contributing to fusion reactor construction researches by determining possibility of actualization of inelastic scattering reaction. In this thesis, differential cross section is measured with TALYS 1.8 nuclear reaction code for neutrons which have 14.1 MeV energy inelastic scattering from 52Cr and 56Fe, neutrons which have 14.6 MeV energy inelastic scattering from 59Co target nucleus. Differential cross section which is measured and experimental differential cross section which is in EXFOR library are compared. As a result of studies, when differential cross sections of target nucleus are compared, it is seen that experimental and theoretical data are compatible.