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 …

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 …

Abstract After the Fukushima-Daiichi event, there has been notable progress in developing
accident-tolerant fuel (ATF) cladding designs to improve light-water reactor (LWR) safety …

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 …

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 …

To optimize the oxidation behavior of chromium-coated Zircaloy-4 alloys under 1200° C high-
temperature steam for accident tolerant fuel (ATF) claddings, Cr coatings with different …

Five CrNb coatings containing different Nb contents were deposited on zircalloy substrate by
magnetron sputtering technology. The effect of Nb content on microstructure, mechanical …

The TiVZrCrAl high entropy alloy (HEA) coatings with different deposition temperatures were
prepared on Zr-4 alloys by using radio frequency magnetron sputtering (RFMS) technology …

Cr coatings were deposited on Zr-4 tubes by arc ion plating to explore the effect of different
aging treatment times at low temperature on the steam oxidation performance of Cr coatings …

Cr-coated zirconium alloys represent a modern approach to enhance cladding safety during
accident scenarios. Two high-power impulse magnetron sputtered Cr-coated Zry-4 systems …