Abstract The Fukushima-Daiichi accident revealed that the zirconium fuel claddings have
the significant safety risk of hydrogen detonation due to the strong oxidation and hydrogen …

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

The oxidation of chromium-coated zirconium-based alloys is studied under steam at
temperatures ranging from 800° C up to 1500° C and for oxidation times ranging from a few …

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 …

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 …

Cr coatings with the thickness of 4.5–9.0 μm and dense/columnar microstructure were
deposited onto Zr alloy by cooled or hot target magnetron sputtering. Steam oxidation tests …

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 …

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

This article reviewed the near-term development status of accident tolerant fuel (ATF)
cladding to increase the safety of nuclear power generation. The key to near-term …