Quantitative residual strain analyses on strain hardened nickel based alloy

Toshio Yonezawa, Takaharu Maeguchi, Toru Goto, Hou Juan

    研究成果: Conference contribution

    4 被引用数 (Scopus)

    抄録

    Many papers have reported about the effects of strain hardening by cold rolling, grinding, welding, etc. on stress corrosion cracking susceptibility of nickel based alloys and austenitic stainless steels for LWR pipings and components. But, the residual strain value due to cold rolling, grinding, welding, etc. is not so quantitatively evaluated. Therefore, authors quantitatively measured and evaluated the residual strain value for strain hardened tensile or torsion specimens of nickel based alloys by applied strain, FWHM of gamma X-ray diffraction, EBSD and Vickers' hardness measurement to make a calibration curve, at first. Using these curves, the residual strain in the heat affected zone of weld joint and cold worked plates, etc., was quantitatively evaluated from the measuring data of Vickers' hardness or EBSD or FWHM of gamma peak in X-ray diffraction. As a result, residual strain value in the heat affected zone of weld joint was evaluated as about 10% of von Mises equivalent strain from FWHM, EBSD and Vickers' hardness measurement. But the residual strain of the 20% and 30 % cold rolled Alloy 600 or TT690 were evaluated about 40% and 60 % of von Mises equivalent strain, respectively.

    本文言語English
    ホスト出版物のタイトル15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
    ページ1666-1678
    ページ数13
    出版ステータスPublished - 2011 12月 1
    イベント15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 - Colorado Springs, CO, United States
    継続期間: 2011 8月 72011 8月 11

    出版物シリーズ

    名前15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
    3

    Other

    Other15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
    国/地域United States
    CityColorado Springs, CO
    Period11/8/711/8/11

    ASJC Scopus subject areas

    • 原子力エネルギーおよび原子力工学
    • 汚染

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