Zircaloy (-2 and -4) spent nuclear fuel cladding is considered by the U. S. Department of Energy as an additional metallic barrier for the containment of radionuclides in the proposed repository at Yucca Mountain, Nevada. Because Zircaloy develops a thick oxide during in-reactor service, hydrothermally oxidized Zircaloy was compared to as-polished Zircaloy under a variety of environmental conditions to evaluate the effect of the oxide film on localized (pitting) corrosion in chloride-containing solutions. Besides cyclic potentiodynamic polarization and potentiostatic tests, open circuit potentials measurements were conducted in air saturated chloride solutions
with the addition of H2O2 and FeCl3. The electrical characteristics of the hydrothermally grown oxide films were examined using electrochemical impedance spectroscopy and measurements of the charge transfer resistance for a redox couple. Stable pitting corrosion in the presence of a thick oxide layer was observed after 40 days in potentiostatic tests but it was not initiated in open circuit tests. Preliminary explanations for this observation are provided.