The influence of the nuclear fuel cladding pre-oxidation on post-LOCA quench resistance was experimentally studied and then modeled. Adopting a separate effect approach, quenched high temperature oxidized samples were axially loaded in a mechanical device. The pre-existing oxide layer shows a complex influence that was interpreted and modeled using a simple approach reproducing the main observed phenomena. A new correlation was established to evaluate the oxygen enriched alpha-phase thickness and the zirconia layer growth is analyzed and modeled. These models and correlations were implemented in a failure prediction model finally compared to experimental results.