Lithium-lead corrosion behavior of zirconium oxide coating after heavy-ion irradiation

For a strict control of tritium migration in fusion reactor fuel systems, permeation barrier coatings have been developed for several decades. In liquid blanket concepts, corrosion the by breeders is serious concern addition to permeation. Furthermore, are exposed high-energy neutrons an actual reactor, which would bring synergy irradiation and corrosion. this study, zirconium oxide (ZrO2) prepared metal organic decomposition were static lithium-lead (Li-Pb) 500 h at 500−600 ºC after iron-ion with damage concentration up 16 displacement per atom room temperature ºC. Corrosion products formed on all samples, their amount stability depended density during Li-Pb exposure. Voids segregated grain boundaries ZrO2 coating. The thicknesses irradiated decreased concentration; therefore, be promoted microstructure change caused heavy-ion irradiation. These results suggest that compatibility degraded under environments.