Seminarium Zakładu Energetyki Jądrowej i Analiz Środowiska

Hypothetical helium migration in uranium dioxide fuel during neutron irradiation in terms of defect trap model

It is known that a large amount of noble gases are retained in the high burn-up fuel. The release of both the helium atoms and the fission gas of xenon atoms behave alike during the annealing process. This lets us infer that migration and release of helium from the fuel under irradiation are also alike the fission gas products – the same mechanisms control these.

Simulation of ion irradiation of Silicon Carbide

Silicon Carbide (SiC) is a promising material for several applications such as nuclear application, electronic and space application. Characterizing and understanding radiation effects and damage creation is crucial for materials application in nuclear. Radiation defects can be studied not only by experiments but also by simulations methods. In the talk, the possible simulation tools to study ion irradiation damage in SiC, like TRIM and LAMMPS will be described.