Zircaloy-4 cladding embrittlement due to inner surface oxidation under simulated loss-of-coolant condition.

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概要

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• 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 Al<SUB>2</SUB>O<SUB>3</SUB> 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 0.131.6 g/cm<SUB>2</SUB>•min.<BR>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 200300 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.<BR>Hydrogen absorbed by the Zircaloy precipitated in the form of fine hydride crystals formed along previous °-phase grain boundaries. Peaks were found in the distribution of hydrogen absorbed on the inner surface, at a distance of 1545 mm upward and downward of the rupture opening. Within this range, the distance was influenced by the oxidation temperature and steam flow rate.

• 一般社団法人 日本原子力学会の論文

著者

• KAWASAKI SATORU

  Division of Cardiology, National Akashi Hospital

• UETSUKA Hiroshi

  Division of Nuclear Safety Research, Japan Atomic Energy Research Institute

• FURUTA Teruo

  Division of Reactor Safety, Japan Atomic Energy Research Institute

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