To support the transition towards low-carbon energy systems, new reactor concepts are being developed to offer greater flexibility and reduced construction costs. Among these, the Lead-cooled Fast Reactor (LFR) stands out for the favourable properties of lead as a coolant and its potential for simplified design. Despite its advantages, several technical challenges remain. This thesis focuses on one of them: the erosion corrosion phenomena induced by heavy liquid metal flow on protective layers within reactor components. One important aspect to investigate is the erosion that the heavy liquid metal flow can induce on the passive-corrosion layers present along the fuel bundles and along the heat exchanger tubes.