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 …

Thermal–hydraulics (TH) experiments have been on the progress to evaluate boiling heat
transfer characteristics of accident tolerant fuel (ATF) candidates for further supporting the …

The conventional Zircaloy cladding may react with coolant in light water reactors and elicit
severe accident at high temperature, which constraint the safe and efficient development of …

Abstract Iron-chromium-aluminum (FeCrAl) alloys are being investigated as cladding
material for urania nuclear fuel in light water power reactors. One extraordinary attribute of …

Corrosion behavior in simulated pressurized water reactor (PWR) primary water was
investigated for stainless steels with 16 and 22 wt% Cr having austenitic, ferritic, and duplex …

Ferritic iron-chromium-aluminum (FeCrAl) alloys and coatings with varying Cr content were
subjected to in-situ irradiation-corrosion with energetic protons or electron beams in …

This work systematically reports grain boundary radiation-induced segregation (RIS), and
insights into RIS mechanisms, in FeCrAl alloys. Recently, FeCrAl alloys have received …

The oxidation resistance of FeCrAl based on alloying composition and oxidizing conditions
is predicted using a combinatorial experimental and artificial intelligence approach. A neural …

The carburization behavior of bare and pre-oxidized APMT has been assessed after long-
term graphite exposure at 1000° C. Bare coupons formed a thick scale after graphite …

The APMT FeCrAl alloy is a cladding candidate for the accident-tolerant fuel (ATF) systems
in light water reactors (LWRs) due to its ability to form a protective Al 2 O 3 film on the …