CORDIS Project
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This project focuses on the investigation of grain boundaries in zirconium alloys used in nuclear reactor cladding. It aims to understand the effects of point defects and alloying elements on material performance under irradiation through advanced modeling techniques.
Stress corrosion and macroscopic growth of cladding materials used in nuclear reactors are topics of technological interest, as the reduction in CO2 and use of green energy is one of the core objectives of the European Union.
Under irradiation, material deterioration is influenced by point defects produced in large quantity and grain boundaries (GBs).
In this context, investigating their interactions is of fundamental importance, which implies identifying the nature of the GBs.
Therefore, in thi…
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