Earthquakes are sources of external acceleration to components of nuclear reactors that can affect structural and material integrity. The core, that holds the fuel in which the nuclear reaction that produces heat occurs, is an intricate system that needs to be better understood in these conditions. The main objective of this work is to investigate the sloshing behavior inside a Lead-cooled Fast Nuclear Reactor (LFR) during an earthquake is conducted. The analysis of the liquid sloshing is very important in the Nuclear Power Plants (NPPs) structures to evaluate the real capacity of dynamic loads bearing and related safety levels as NPP integrity of structures, systems and components must be ensured in case of any design condition.
