Theory-guided bottom-up design of the FeCrAl alloys as accident tolerant fuel cladding materials
Sign Up to like & getrecommendations! Published in 2019 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2019.01.002
Abstract: Abstract As interest in new generations of nuclear reactors is increasing worldwide, development of accident tolerant fuel (ATF) cladding materials is crucial but suffers from large amounts of time and experimental efforts. Here, we present… read more here.
Keywords: tolerant fuel; cladding materials; accident tolerant; fecral alloys ... See more keywords
Effect of aluminum content on dislocation loops in model FeCrAl alloys
Sign Up to like & getrecommendations! Published in 2019 at "Nuclear materials and energy"
DOI: 10.1016/j.nme.2019.100718
Abstract: Abstract Five kinds of iron-chromium-aluminum (FeCrAl) alloy samples with different contents of aluminum (Al)—Fe-12Cr, Fe-12Cr-2Al, Fe-12Cr-4Al, Fe-12Cr-6Al, and Fe-12Cr-8Al—were designed and prepared. All samples were then irradiated with 200 keV argon ions (Ar2+) to the fluence… read more here.
Keywords: dislocation; effect aluminum; content; dislocation loops ... See more keywords
Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors
Sign Up to like & getrecommendations! Published in 2023 at "Materials"
DOI: 10.3390/ma16093497
Abstract: In order to meet the growing energy demand, more environmentally friendly and efficient GEN-IV reactors have emerged. Additionally, nuclear structural materials need larger more safety margins for accident scenarios as a result of the Fukushima… read more here.
Keywords: recent progress; fecral alloys; creep properties; ods fecral ... See more keywords