Effects of contents of Al, Zr and Ti on oxide particles in Fe–15Cr–2W–0.35Y2O3 ODS steels

FeCrAl oxide dispersion strengthened (ODS) steel is one of the most promising candidate cladding materials of generation IV nuclear reactors because of its excellent resistance to not only corrosion but also creep and irradiation due to the ultrahigh density nanometer-scale oxides. Effects of the co...

Ausführliche Beschreibung

Gespeichert in:

Bibliographische Detailangaben
Veröffentlicht in:	Journal of nuclear materials 2020-04, Vol.531, p.152025, Article 152025
Hauptverfasser:	Dou, Peng, Jiang, Shaomin, Qiu, Lanlan, Kimura, Akihiko
Format:	Artikel
Sprache:	eng
Schlagworte:	Aluminum Corrosion resistance Creep (materials) Crystal structure Crystallography Dispersion hardening steels Iron Irradiation Nuclear electric power generation Nuclear reactors Oxide dispersion strengthening Oxides Radiation Scale (corrosion) Steel Thermal stability Titanium Transmission electron microscopy Zirconium oxides
Online-Zugang:	Volltext
Tags:	Tag hinzufügen Keine Tags, Fügen Sie den ersten Tag hinzu!

Schreiben Sie den ersten Kommentar!