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 review describes recent progress on understanding and quantification of the various
phenomena that take place during plasma electrolytic oxidation, which is in increasing …

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 …

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 …

Abstract (Cr/CrN) n multilayer coatings were prepared on Zr-4 alloy using magnetron
sputtering and effects of this multilayer architecture on the microstructure, mechanical …

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 …

Abstract The Cr coatings (4.5–9.0 µm-thick) with porous/columnar and dense/columnar
microstructure were deposited on Zr alloy. Oxidation was performed at 900, 1050, 1200 and …

Zirconium-based alloys (Zr alloys) are key materials in the nuclear industry due to their
thermal stability, mechanical durability, and low thermal neutron cross section. However …

Thick Cr coatings sized∼ 27 μm were deposited on Zr-4 substrates by magnetron sputtering
to improve the high-temperature oxidation resistance of Zr alloys for accident tolerant fuel …