With high mechanical strength, good corrosion resistance and small thermal neutron
absorption cross-section, zirconium based alloys are widely used as the nuclear structural …

Abstract Delayed Hydride Cracking (DHC) behaviour of Zr-2.5 Nb Pressure Tube (PT)
material used in Indian 200MWe Pressurised Heavy Water Reactor (PHWR) containing …

Formation of partially constrained precipitates such as hydride blisters and oxide nodules
have been reported on surfaces of Zr-alloy components of pressurised heavy water reactors …

Hydrogen diffusion studies in Zr-2.5% Nb alloy pressure tube material are important inputs
for modeling localized embrittlement phenomenon manifested in pressure tubes. The …

Abstract The Zr-2.5 Nb alloy pressure tubes of Indian Pressurized Heavy Water Reactors
were manufactured from double melted ingots initially and subsequently from quadruple …

In this work, influence of hydrogen and temperature on the fracture toughness parameters of
unirradiated, cold worked and stress relieved (CWSR) Zr–2.5 Nb pressure tube alloys used …

The stress fields of expanding (precipitation) and contracting (dissolution) hydride plates
were computed by finite element method using Zr–H solid solution and hydride properties at …

In this work, a microstructurally sensitive computational model is developed to simulate
delayed hydride cracking (DHC) in Zr-2.5 Nb alloy. The model is validated by comparing …

Zirconium alloys are extensively utilized as structural materials in nuclear applications due
to their exceptional mechanical strength, corrosion resistance, and low thermal neutron …

In Part I of the present article, we formulated a continuum-based computational model for
stress-and temperature-directed diffusion of hydrogen in metals that form brittle binary …