The mechanical integrity and corrosion behavior in nuclear reactor environments of zirconium alloys can be related to the formation and morphology of intermetallic hydrides which precipitate in them. The nature of these hydrides has been studied and the results summarized in the literature. However, there still seems to be some uncertainty as to the type of hydride which precipitates in low hydrogen content zirconium alloys; i.e., whether it is the face-centered-cubic ∫ phase), designated ZrH1.5, or the face-centered tetragonal hydride, γ‘, of c/a around 1.08. The composition of γ’ was originally placed at ZrH0.5 but was later shown by neutron diffraction to be non-stoichiometric and extending to ZrH.
Corrosion behavior of Mg-Zn-Zr-RE alloys under physiological environment – Impact on mechanical integrity and biocompatibility
