Hydrogen absorbed into zirconium alloy nuclear fuel cladding as a result of the waterside
corrosion reaction can affect the properties of nuclear fuel, principally through the …

The zirconium alloys used in nuclear industry include mainly Zr–Sn and Zr–Nb alloys of
different chemical composition, microstructure and susceptibility to both hydrogen …

In an attempt to develop an accident-tolerant fuel (ATF) that can delay the deleterious
consequences of loss-of-coolant-accidents (LOCA), multilayer coatings were deposited onto …

With the aim of improving the oxidation resistance of fuel cladding in a light water reactor,
CrN coating, which has good uniformity and compactness with an average thickness of …

In an attempt to develop a nuclear fuel cladding that is more tolerant to loss-of-coolant-
accidents (LOCA), ceramic coatings were deposited onto a ZIRLO™ 1 substrate by cathodic …

Zirconium alloys are susceptible to hydrogen embrittlement and hydride precipitation. The
precipitation of hydrides is accompanied by a transformation strain, but the contribution of …

The ingress of hydrogen during corrosion in service can degrade the mechanical properties
of zirconium alloy nuclear fuel cladding because of the formation of brittle hydrides. The …

Zircaloy is extensively used as a nuclear fuel cladding tube material. The fuel cladding
encapsulates radioactive fuel pellet and it is resorted to an exceptionally harsh environment …

Hydrides are at the center source of mechanical degradation affecting Zr-based nuclear fuel
cladding integrity during in-reactor service and even spent fuel storage. This study presents …

The orientation and distribution of hydrides formed in zirconium alloy nuclear fuel cladding
can strongly influence material behavior and in particular resistance to crack growth. The …