Advanced Modelling of 238U(n,f) in a Fast Reactor Application

Fast neutron reactors, as a possible future solution on energy demand of human society, based on fission process of $^{238}$U, request new and reliable nuclear data necessary for new generation reactors design. Fission process induced by fast neutrons on $^{238}$U was investigated. Fission observables like cross sections and their uncertainties, fission fragment mass distribution, prompt neutrons emission, isomer ratios and other parameters were obtained by using Talys computer code or programs realized by authors. Then the production of isotopes like $^{135,133}$Xe, $^{99}$Mo, $^{131}$I, $^{89}$Y as well as yields of fissile nuclei were evaluated. Obtained theoretical evaluations are compared with existing experimental data