Intermediate temperature corrosion behaviour of Fe-12Cr-6Al-2Mo-0.2Si-0.03Y alloy (C26M) at 300–600 °C
Source abstract
Abstract
Abstract Iron-chromium-aluminium alloys are of interest to the nuclear materials community due to their resistance to high temperature steam oxidation and good mechanical properties under irradiation. The present work investigates oxide formation on Fe-12Cr-6Al-2Mo-0.2Si-0.03Y alloy at temperatures relevant to light water reactor cladding operation following extended aging to assess growth kinetics, chemical composition, and oxide microstructure. Oxide growth follows a logarithmic time dependence. When the oxidization temperature is 400 °C or below, the oxide is amorphous. At 500 °C or above, crystalline α-Al2O3 oxide film develops and the correlated logarithmic rate constant decreases significantly, indicating enhanced oxidation resistance of the formed oxide film.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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