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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Bibliographic Details
Main Author: YANG Yu1, 2, ZHANG Yan’ge2, LI Xiangyan2, XU Yichun2, , , WU Xuebang2, LIU Changsong2
Format: Article
Language:English
Published: Editorial Board of Atomic Energy Science and Technology 2024-12-01
Series:Yuanzineng kexue jishu
Subjects:
Online Access:https://yznkxjs.xml-journal.net/article/doi/10.7538/yzk.2024.youxian.0202