Stability Study of bcc-Fe/FeCr2O4 Interface Based on First Principles
Ferritic/martensitic (F/M) steels are regarded as the ideal candidates for structural materials in advanced nuclear reactors because of their high thermal conductivity, low thermal expansion and high resistance to irradiation.However, in contact with oxygenated coolants (air, water and liquid metals), they undergo oxidative corrosion and multiple l