Computer simulation of fluorite-based oxides for nuclear applications

In this chapter the methodology and the main results of our classical molecular dynamics (MD) calculations employing Born-Mayer-Huggins or Busing-Ida type interatomic potential function are presented and discussed to elucidate some basic thermo-physical properties of fluorite-type actinide- and zirconia-based oxide nuclear fuels with intrinsic or extrinsic lattice defects. These include; oxygen and metal diffusion behavior for bulk and grain boundaries of UO₂, its based UO₂-PuO₂ mixed oxide and related multi-component oxides and yttria-stabilized zirconia, etc., their thermal conductivity in both equilibrium and non-equilibrium MD schemes in connection with their oxygen non-stoichiometry, and the melting phenomena of UO₂ studied by solid/liquid two-phase simulation (TPS) method.