AlO Regions/Grains in ODS Steel PM2000 Irradiated With Fe Ions at 700 °C
Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, ISSN: 1073-5623, Vol: 54, Issue: 3, Page: 952-961
2023
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Article Description
Oxide dispersion strengthened (ODS) steel is one of the candidate structural materials for Generation-IV nuclear reactors. The microstructure of as-rolled PM2000 steel irradiated with 3.5 MeV Fe ions at 700 °C to 0.75 dpa was studied using transmission electron microscopy in combination with the microstructure of the unirradiated steel. In difference to unirradiated steel, white blocky regions appeared in the irradiated steel and were identified to belong to AlO oxide with a base-centered monoclinic crystal structure. The irradiation induced the formation of the AlO regions in the steel. Segregation of alloy elements in the irradiated steel, characterized by Ti enrichment at the AlO/Fe interface, was observed. Three types of dispersed phases were found in the AlO regions, respectively: Fe-rich MC and Cr-rich MC carbides with a simple orthorhombic lattice, and YAlO oxide with an orthorhombic structure. Fe-rich MC and Cr-rich MC carbides were irradiation-induced precipitates. In order to better evaluate the AlO layer on the surface of ODS steel under irradiation conditions, it is more reasonable to study the AlO layer grown on the steel surface during irradiation.
Bibliographic Details
Springer Science and Business Media LLC
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