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Observation of the spatial distribution of hydrogen in Zircaloy-2 oxidized in H2O steam at 723 K by a technique of tritium microautoradiography

Authors
Journal
Journal of Nuclear Materials
0022-3115
Publisher
Elsevier
Publication Date
Volume
248
Identifiers
DOI: 10.1016/s0022-3115(97)00129-3
Keywords
  • Part Ii. Interfacial Effects In Fission Energy Systems Section 11. Cladding Corrosion Under Irradiat

Abstract

Abstract The spatial distribution of hydrogen in Zircaloy-2, which was oxidized in H 2O steam at 723 K and quenched down to room temperature, was examined by a technique of tritium autoradiography. Tritium was introduced into the specimen through the oxide layer by the cathodic charging method using tritium water at room temperature. The radiograph of the cross-section was observed by a scanning electron microscope. Hydrogen was densely distributed on the grain boundary and in the grain of the inner base alloy, but it was scarcely distributed in the oxide layer. Hydrogen was locally distributed, however, in the region corresponding to the intermetallic precipitates embedded in the oxide layer. The mechanism of penetration of tritium through the oxide layer during the cathodic charging was discussed.

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