Numerical estimation of fission fragments flux on surface of fuel cladding

Abstract

Swift heavy ion beams become an integral part of R&D work related to radiation material science in plutonium and other minor actinides transmutation or radiation tests of candidate materials for future generations of nuclear reactors. In particular, heavy ions accelerated to energies about 1 MeV/u can be successfully used to simulate a damage induced by fission fragments in nuclear materials, which requires knowledge of the flux and mass, energy and angle distributions of fission fragments crossing the border of the fuel pellets. This work presents a numerical estimation of mass-energy-angle dependent yield of fission fragments on a fuel-cladding interface, as well as their ranges and flux through the fuel-cladding border