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 metal...
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Format: | Article |
Language: | English |
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Editorial Board of Atomic Energy Science and Technology
2024-12-01
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Series: | Yuanzineng kexue jishu |
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Online Access: | https://yznkxjs.xml-journal.net/article/doi/10.7538/yzk.2024.youxian.0202 |