Zirconium-based alloys have served the nuclear industry for several decades due to their
acceptable properties for nuclear cores of light water reactors (LWRs). However, severe …

FeCrAl alloys exhibit outstanding high-temperature oxidation resistance and impressive
mechanical strength, rendering them as forefront materials with broad applicability across …

The Mg alloys with combination of high strength and excellent irradiation resistance are
currently required for research reactors. In this work, the novel Mg-3Mn-0.5 Ca alloy with a …

Accident-tolerant fuel (ATF) cladding materials aim to improve fuel reliability and safety
during accident scenarios in water-cooled reactors. These ATF cladding should also perform …

Six kinds of FeCrAl coatings with different Cr and Al contents were irradiated by 6 MeV Au-
ions with a damage level of 20 dpa. The results showed that the surface roughness and …

Post–neutron irradiation examination is performed on advanced accident-tolerant fuel (ATF)
cladding iron-chromium-aluminum (FeCrAl) alloys with∼ 10–13at.% Cr,∼ 10–12 at.% Al,∼ …

Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an
accident tolerant fuel is and the benefits and detriments of each concept. The book begins …

FeCrAl alloy is one of the promising cladding materials in the advanced nuclear reactors.
Here we compare the irradiation response of the nanolaminate (NL) and coarse-grained …

Abstract Iron-chromium-aluminum (FeCrAl) alloys with different content of niobium (Nb)—0,
0.4 wt%, 0.8 wt%, and 1.2 wt%—were designed and prepared. All samples were then …

This article investigates the fuel-cladding chemical interaction (FCCI) behavior of two
commercial FeCrAl alloys, APMT composition (Fe-21Cr-5Al-3Mo wt.%) and C35M (Fe-13Cr …