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 primary objective of this article is to gather comprehensive experimental and theoretical
data on the fracture process of hydrogenated zirconium alloys at micro-and nano-levels and …

The fracture behavior of Zr-2.5 Nb pressure tube (PT) material containing radial hydrides
with hydrogen concentrations between 30 and 300wppm was evaluated between 25 and …

The mechanical integrity of post hydride reorientation cladding was investigated for various
amounts of charged hydrogen and their morphologies. The specimens were charged with …

The zirconium alloys used in the core of nuclear reactors are susceptible to hydride
formation and hydrogen embrittlement. Depending on the loading condition, zirconium …

Hydride precipitation within zirconium alloys affects ductility and fracture behavior. The
complex distribution of hydrides and their interaction with defects, such as dislocations, have …

Hydrogen-induced variations in mechanical behavior of zirconium alloys impose detrimental
influence on nuclear fuel cladding integrity. This work reports a disappearance of intrinsic …

During normal reactor operation, high-temperature water corrosion of the zirconium-based
fuel cladding generates hydrogen, some of which diffuses into the metal. Hydrogen, both in …

Abstract The connection between Zr–2.5% Nb pressure tubes and modified martensitic
stainless steel-403 end fittings in Pressurized Heavy Water Reactors (PHWRs) at the rolled …

Zirconium alloys are widely used in nuclear water reactors as cladding materials. The
cladding materials will absorb hydrogen from high temperature water during the operation of …