Results 81 to 90 of about 324 (179)

The effects of Cr and Nb on the microstructure, mechanical properties, and oxidation behavior of FeCrAl alloys

open access: yesNuclear Engineering and Technology
This article explores the effects of Cr and Nb on the microstructure, mechanical properties, and oxidation behavior in 1200 °C steam of FeCrAl alloys. The experimental results indicate that Cr is solidly dissolved in the matrix, has minimal impact on the
Chundong Wang   +7 more
doaj   +1 more source

High-Temperature Tensile Properties and Serrated Flow Behavior of FeCrAl Alloy for Accident-Tolerant Fuel Cladding

open access: yesApplied Sciences
The development of FeCrAl alloys has commenced for use as nuclear fuel cladding material, intended to serve as an enhanced accident-tolerant alternative to Zr-based alloys. In this study, the Fe-13Cr-4Al alloy, specifically designed for advanced accident-
Mengyu Chai   +5 more
doaj   +1 more source

Benchmarking SiCf/SiC, FeCrAl, and Cr-coated Zr alloy claddings: evaluating thermomechanical properties and high-temperature oxidation resistance of next-generation nuclear claddings

open access: yesAdvances in Physics: X
Although nuclear energy is a clean and sustainable source, inherent safety concerns have long been recognized and were critically highlighted by the Chernobyl and Fukushima accidents.
Ghadeer Hegab Mohamed   +5 more
doaj   +1 more source

Effect of densification technology on the microstructure and mechanical properties of high-entropy (Ti, Zr, Hf, Nb, Ta)C ceramic-based cermets

open access: yesOpen Ceramics
High-entropy ceramic-based cermets represent a new and promising direction in improving the mechanical properties of conventional hardmetals through the formation of complex microstructures during synthesis. This has been systematically studied in two Co-
Dmytro Vedel   +9 more
doaj   +1 more source

Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors. [PDF]

open access: yesMaterials (Basel), 2023
Jia H   +5 more
europepmc   +1 more source

Database on Performance of Neutron Irradiated FeCrAl Alloys [PDF]

open access: yes, 2016
Kevin G. Field   +4 more
openaire   +1 more source

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