PRELIMINARY CHARACTERIZATION OF ADVANCED ALLOYS AND COATINGS FOR STRUCTURAL MATERIAL APPLICATION IN LFR

The Lead-cooled Fast Reactors are one of the most promising Gen. IV nuclear systems, currently under development. They can ensure enhanced performances and minimal waste production, but they also have some issues to be addressed. The long-term degradation process caused by Pb corrosion effects, in structural materials facing liquid lead is one of the most critical. The present state of the art showed that commercial stainless steels as AISI 316L and 15-15Ti uncoated can be adopted as structural materials in lead environments below 500 °C, beyond which they start to experience dissolution of constituting alloying elements (e.g., Ni, Cr, Fe).

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