Electron micro autoradiographic observation of tritium distribution on alloy X750

T. Yonezawa, Y. Yamaguchi, Y. Iijima

    研究成果: Conference contribution

    9 被引用数 (Scopus)

    抄録

    In order to clarify the mechanisms of intergranular stress corrosion cracking of Alloy X750 in high temperature water, the authors have studied the relationship between the distribution of hydrogen and the microstructure of grain boundary precipitates by using electron micro autoradiographic technology. Two types of Alloy X750 with different heat treatment history were prepared. Which is sensitive to the stress corrosion cracking in high temperature water, which has incoherent precipitates other than M23C6 discretely exist at the grain boundaries. The other type has excellent resistance to the stress corrosion cracking and has coherent M23C6 precipitates which semi-continuously exist at the grain boundaries. Tritium and hydrogen were charged into these specimens at room temperature by cathodic charging method. After the charging, specimens attached by the sensitive film (monolayer of fine silver bromide grains film) were kept in a dark box for about 10 days. The distribution of Ag grains on the specimen was observed by electron probe microanalyzer and transmission electron microscope. For the specimens which are sensitive to the stress corrosion cracking resistance, the Ag grains existed on the grain boundaries, however, for the specimens which have excellent resistance to the stress corrosion cracking, the Ag grains were not recognized at the grain boundaries. From this evidence, it seems that hydrogen trapping behaviour at the grain boundaries affects the stress corrosion cracking resistance.

    本文言語English
    ホスト出版物のタイトルProc 6 Int Symp Environ Degrad Mat Nucl Power Syst Water React
    編集者Robert E. Gold, Edward P. Simonen
    出版社Publ by Minerals, Metals & Materials Soc (TMS)
    ページ799-804
    ページ数6
    ISBN(印刷版)0873392582
    出版ステータスPublished - 1993 12月 1
    イベントProceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - San Diego, CA, USA
    継続期間: 1993 8月 11993 8月 5

    出版物シリーズ

    名前Proc 6 Int Symp Environ Degrad Mat Nucl Power Syst Water React

    Other

    OtherProceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
    CitySan Diego, CA, USA
    Period93/8/193/8/5

    ASJC Scopus subject areas

    • 工学(全般)

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