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

K. Isobe*, Y. Hatano, M. Sugisaki

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

7 Scopus citations

Abstract

The spatial distribution of hydrogen in Zircaloy-2, which was oxidized in H2O 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.

Original languageEnglish
Pages (from-to)315-318
Number of pages4
JournalJournal of Nuclear Materials
Volume248
DOIs
StatePublished - 1997/09/01

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • General Materials Science
  • Nuclear Energy and Engineering

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