The motivation for transitioning away from zirconium-based fuel cladding in light water
reactors to significantly more oxidation-resistant materials, thereby enhancing safety …

Abstract Zirconium-based (Zr-based) alloys have been widely used as materials for the key
components in light water reactors (LWRs), such as fuel claddings which suffer from …

Coatings with thicknesses between a few microns and∼ 10 μm deposited on a Zircaloy-4
substrate have been studied with the objective to provide a significant reduction in the …

Chongchong Tang received his Master's degree in metallurgical engineering from the
Northeastern University, China, in 2014. He is currently a PhD student in the IAM-AWP of the …

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 …

Oxidation kinetics and microstructural evolution of cold sprayed Cr coatings on Zircaloy-4 at
1130–1310° C in flowing steam at atmospheric pressure have been studied. The study is …

Abstract AREVA NP (Courbevoie, Paris, France) is actively develo** several enhanced
accident-tolerant fuels cladding concepts ranging from near-term evolutionary (Cr-coated …

Cr-coated Zircaloy-4 samples are prepared by vacuum arc plasma deposition and their
microstructure, corrosion resistance and oxidation behavior are investigated. The as …

Cr coatings have been deposited on the outer surface of zircaloy-4 tube with well control of
thickness variations along the tube axis. A series of samples have been oxidized in high …

In an attempt to develop an accident-tolerant fuel (ATF) that can delay the deleterious
consequences of loss-of-coolant-accidents (LOCA), multilayer coatings were deposited onto …