In this study, a Cr-CrN-Cr coating was fabricated on Zr alloys to restrain the Cr-Zr
interdiffusion of Cr-coated Zr alloys. The early stage diffusion, decomposition, and oxidation …

The isothermal oxidation behavior of the Cr-coated Zircaloy-4 at 1200° C in steam is
comprehensively investigated. Oxidation kinetics transition is observed when outward …

In this study, corrosion tests were performed on Cr-coated Alloy 800 H in 500° C
supercritical water, containing 6000 mg∙ L− 1 oxygen, for 500 h. After exposure, the structure …

The isothermal steam oxidation behavior of chromium-coated zirconium alloy cladding at
1200℃ is studied. The cladding substrate is Zr-1 Nb alloy with outer diameter of 9.5 mm and …

Chromium-coated zirconium alloys are one of the promising candidates for accident-tolerant
fuel cladding (ATF) tubes for light water reactors (LWRs). In this study, the high temperature …

textured Cr-coating was deposited on Zr-based nuclear fuel cladding and went through
steam oxidation at 1200° C. The formed Cr 2 O 3 layer exhibited thickening-thinning …

The oxidation and interdiffusion behavior of Cr-and Cr/Mo-coated Zr single bond 1Nb
zirconium alloy were investigated. A single-layer Cr (8 um) and multilayer Cr (8 μm)/Mo (3 …

This article investigates the fuel-cladding chemical interaction (FCCI) behavior of two
commercial FeCrAl alloys, APMT composition (Fe-21Cr-5Al-3Mo wt.%) and C35M (Fe-13Cr …

Cr-coatings with distinct crystallographic fiber textures were deposited on zirconium nuclear
fuel cladding material. The< 100> textured Cr-coating demonstrated superior properties to …

As a safe, clean, efficient and low-carbon energy, nuclear power is gaining increasing
interest in global energy development. However, working in the extremely harsh …