The safety of nuclear power plants has put forward new requirements for the corrosion
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …

Abstract The ZrO 2/Cr bilayer coating on Zr–1Nb alloy fabricated by plasma electrolytic
oxidation and filtered cathodic vacuum arc deposition duplex treatments had good steam …

Cr-coated M5 Framatome 1 cladding materials are studied and developed within the CEA-
Framatome-EDF French nuclear fuel joint program as Enhanced Accident Tolerant Fuel …

The breakaway oxidation of Zircaloy-4 and M5 Framatome alloys oxidized in flowing steam
around 1000° C was studied. The influences of oxidation temperature between 950 and …

The oxidation behavior of zirconium alloy in high-temperature steam plays a dominant role
in the operation of nuclear reactors under accident conditions. The present work …

The PEO/Cr composite coating on Zr–1 Nb alloy prepared by plasma electrolytic oxidation
(PEO) and filtered cathodic vacuum arc deposition (FCVAD) technologies exhibited good …

Zirconium-based alloys are widely used for fuel claddings particularly in pressurized water
reactor. This study investigates the oxidation characteristics of Zr-4 and Zr-Sn-Nb alloy in …

Loss-of-coolant accident (LOCA) modelling forms a pivotal element in the licensing of light
water reactor technologies. Within this context, the National Nuclear Laboratory has further …

Non-contact temperature measurement in a nuclear reactor is still a huge challenge
because of the numerous constraints to consider, such as the high temperature, the steam …

Highly-ordered and hexagonally close-packed nanoporous zirconium oxide layer is formed
on the surface of zirconium alloy by anodization, and the anti-oxidation behavior of the …