Study of (n,f) reaction cross sections for 232Th, 235U, 238U and 239Pu target nuclei

Nuclear fission is a major issue for both nuclear plants and nuclear weapons. The knowledge of factors that are important to understand the production of fissile material and nuclear waste management are important. This study aims on the calculating the fission cross sections that will help to find safe handling knowledge of fission material. From this point of view both technical and historical progress were discussed in obtaining fissile material. The cross sections were calculated by using TALYS 1.4 and 1.6 computer code. In this study, 232Th,235U, 238U and 239Pu neutron-induced fission of nuclei cross sections were calculated in the energy range of 0-14 MeV and compared with experimental data. The calculated cross section is substantially responsive to the literature.