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 …

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 …

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 …

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 The Cr-Zr interaction of two types of Cr coated Zr alloy accident tolerant fuel (ATF)
claddings, deposited by cold spraying and magnetron sputtering, was studied in argon 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 …

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 …

The transient oxidation behavior of magnetron-sputtered chromium-coated Zircaloy-4 was
studied in steam up to 1600° C, and the microstructural evolution of the coating-substrate …

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 …

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 …