Hydrogen–damage interactions in yttria-stabilized zirconia

Hydrogen diffusion and accumulation in oxidized Zr(ZrO2) and oxide–metal interfaces lead to hydrogen induced cracking in Zr-based compounds that are extensively used in nuclear reactors. In this study, the interaction of hydrogen with irradiation damage in (0 0 1) single crystals of yttria-stabilized zirconia (Y–ZrO2) has been investigated as a function of damage accumulation and temperature. Samples were irradiated with 40 keV hydrogen ions at a temperature of 120 K to ion fluences of 5×1016 and 1×1017 ions/cm2, and isochronal experiments were performed in the temperature range from 300 to 770 K in 100 K steps. Damage accumulation and hydrogen profile measurements indicate unusual damage recovery behavior, pinning of hydrogen by damage, and surface deformation due to hydrogen blisters and bubbles.