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

P Dou, S Jiang, L Qiu, A Kimura - Journal of Nuclear Materials, 2020 - Elsevier
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 …
被引用次数：51 相关文章

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

P Dou, S Jiang, L Qiu, A Kimura - Journal of Nuclear …, 2020 - ui.adsabs.harvard.edu
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 …