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 …

Zr–Nb alloy is successfully used as structural materials in nuclear reactors. However, its
widespread application is restricted by corrosion due to complex in-pile environments. This …

Sixteen kinds of FeCrAl coatings with different Cr and Al contents were prepared by the
magnetron sputtering method, and the thermal shock resistance and static lead‑bismuth …

The corrosion behavior of the FeCrAl coating with different Cr and Al contents before and
after Au-ions irradiation was investigated in static LBE. The grain of the irradiated coating …

The corrosion behavior of Fe-13Cr-4Al-2.2 Mo, a candidate cladding material for accident
tolerant fuel, doped with varying concentrations of Nb (0, 0.5, 1.0, and 1.5 wt%), was …

FeCrAl alloy coatings are widely used for their excellent oxidation resistance at high
temperatures, but they can suffer from rapid material degradation due to breakaway …

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

After the Fukushima explosion, the research and development of accident tolerant fuel (ATF)
cladding has become a hot spot in the nuclear field. In this work, corrosion behavior of …

The present study investigated the microstructure and oxidation behavior of the
CoCrFeMnNi high-entropy alloy (HEA) prepared by selective laser melting (SLM). The …

Nuclear energy is presently the single major low-carbon electricity source in Europe and is
overall expected to maintain (perhaps eventually even increase) its current installed power …