Article

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

Antonino MeliPolytechnic University of Turin – Energy Department,newcleo – Thermal Hydraulic test operationS. BassiniChiara CiantelliMassimo AngioliniM. Tarantino

The Proceedings of the International Conference on Nuclear Engineering (ICONE)conference2023en

ABI

Abstract

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).

Topics

Metallurgical Processes and Thermodynamics

Identifiers

DOI: 10.1299/jsmeicone.2023.30.1935

Citations and references

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