Effects of Weld-overlay Cladding on the Structural Integrity of Reactor Pressure Vessels during Pressurized Thermal Shock

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Numerical simulations by thermal-elastic-plastic-creep analysis using finite element method (FEM) have been performed to evaluate residual stress distributions in a reactor pressure vessel (RPV) caused by weld-overlay cladding, post-weld heat treatment (PWHT), hydrostatic test, operation and pressurized thermal shock (PTS). The weld-overlay cladding gives tensile stress in the cladding layer and base metal near the cladding. Using the calculated welding residual stress, stress intensity factors (SIFs) during PTS have been computed based on the influence function method. The maximum value of SIF during PTS with weld-overlay cladding is higher than that without weld-overlay cladding. According to the structural integrity assessment procedure of an RPV against PTS, a comparison has been also made by defining a temperature margin. The result indicates that the residual stress makes the temperature margin smaller in a few degree C which may be within the range of the margin originally put in the structural integrity assessment procedure.

収録刊行物

  • 溶接学会論文集 : quarterly journal of the Japan Welding Society

    溶接学会論文集 : quarterly journal of the Japan Welding Society 27(2), 245s-250s, 2010-01-20

    一般社団法人 溶接学会

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各種コード

  • NII論文ID(NAID)
    10030149264
  • NII書誌ID(NCID)
    AN1005067X
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    02884771
  • データ提供元
    CJP書誌  J-STAGE 
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