Kodai Toyota 1 and Naoyuki Hashimoto 1
1 Faculty of Engineering, Hokkaido University
Fe-Cr-Al ferritic steel is one of candidate structure materials for next-generation nuclear and fusion reactor due to its good corrosion resistance by alumina layer formed on surface. While, the effect of aluminum on microstructural evolution under neutron irradiation seems not to be clear. In this study, in-situ electron irradiation experiment was carried out for Fe-12Cr-5Al and Fe-12Cr in order to investigate the difference of damage evolution between with and without aluminum. Electron irradiation to Fe-12Cr-5Al resulted in less number density and larger size of dislocation loops compared with that in Fe-12Cr. This suggested that aluminum in matrix would have a strong interaction with vacancy, leading to more interstitial flow into dislocation loops.
iron chromium aluminum alloy, irradiation damage
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