Embrittlement of Zircaloy-4 cladding by oxidation of the inner surface occurring in an LWR loss-of-coolant accident was studied using simulated fuel containing of Al2O3 pellets sheathed in Zircaloy-4 specimen cladding, filled with Ar gas, and sealed. This simulated fuel rod was heated from outside until the isothermal oxidation temperature between 880 and 1,167°C was obtained after the cladding burst. This exposed the inner surface of the cladding to the environmental atmosphere, provided by steam flowing at a constant rate in the range of 0.13~1.6g/cm2-min. The embrittlement of the specimen due to inner surface oxidation is influenced primarily by the amount of hydrogen absorbed by the Zircaloy-4. Ring compression tests conducted at 100° C on test pieces constituted of sliced sections of oxidized specimen showed that Zircaloy containing more than 200~300 wt.ppm of absorbed hydrogen became brittle when oxidized at temperatures above 1,000°C. In the range of oxidation temperature 932 to 972°C, brittleness did not appear below 500~750 wt.ppm absorbed hydrogen. Hydrogen absorbed by the Zircaloy precipitated in the form of fine hydride crystals formed along previous β-phase grain boundaries. Peaks were found in the distribution of hydrogen absorbed on the inner surface, at a distance of 15~45 mm upward and downward of the rupture opening. Within this range, the distance was influenced by the oxidation temperature and steam flow rate. © 1981, Taylor & Francis Group.
CITATION STYLE
Uetsuka, H., Furuta, T., & Kawasaki, S. (1981). Zircaloy-4 cladding embrittlement due to inner surface oxidation under simulated loss-of-coolant condition. Journal of Nuclear Science and Technology, 18(9), 705–717. https://doi.org/10.1080/18811248.1981.9733309
Mendeley helps you to discover research relevant for your work.