Hydrogen-damage interactions in yttria-stabilized zirconia

Hydrogen diffusion and accumulation in oxidized Zr(ZrO2) and oxide-metal in terfaces lead to hydrogen induced cracking in Zr-based compounds that are e xtensively used in nuclear reactors. In this study, the interaction of hydr ogen with irradiation damage in (001) single crystals of yttria-stabilized zirconia (Y-ZrO2) has been investigated as a function of damage accumulatio n and temperature. Samples were irradiated with 40 keV hydrogen ions at a t emperature of 120 K to ion fluences of 5 x 10(16) and 1 x 10(17) ions/cm(2) , and isochronal experiments were performed in the temperature range from 3 00 to 770 K in 100 K steps. Damage accumulation and hydrogen profile measur ements indicate unusual damage recovery behavior, pinning of hydrogen by da mage, and surface deformation due to hydrogen blisters and bubbles. (C) 200 1 Published by Elsevier Science B.V.