Hydrogen diffusion and accumulation in oxidized Zr and ZrO2/Zr interfaces lead to hydrogen induced cracking in Zr-based alloys that are extensively used in nuclear reactors. In this study, the interaction of hydrogen with irradiation damage in (001) single crystals of yttrium-stabilized zirconia, Y-ZrO2, has been investigated as a function of damage accumulation and annealing temperature. Samples were irradiated with 40 keV hydrogen ions at a temperature of 1220 K to ion fluences of 5x10 16 and 1x10 17 ions/cm2, and isochronal annealing 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.
Revised: February 27, 2001 |
Published: March 1, 2001
Citation
Shutthanandan V., S. Thevuthasan, J.S. Young, T.M. Orlando, and W.J. Weber. 2001.Hydrogen-Damage Interactions in Yttrium-Stabilized Zirconia.Journal of Nuclear Materials 289, no. 1-2:128-135.PNNL-SA-33183.