• Title of article

    Current research on environmentally assisted cracking in light water reactor environments

  • Author/Authors

    Zhang، J. Y. نويسنده , , Chung، H.M. نويسنده , , Shack، W.J. نويسنده , , Chopra، O.K. نويسنده , , Kassner، T.F. نويسنده , , Park، J.H. نويسنده , , Brust، F.W. نويسنده , , Dong، P. نويسنده ,

  • Issue Information
    دوهفته نامه با شماره پیاپی سال 1999
  • Pages
    -204
  • From page
    205
  • To page
    0
  • Abstract
    The effect of dissolved oxygen level on fatigue life of austenitic stainless steels is discussed and the results of a detailed study of the effect of the environment on the growth of cracks during fatigue initiation are presented. Initial lest results are given for specimens irradiated in the Halden reactor. Impurities introduced by shielded metal arc welding that may affect susceptibility to stress corrosion cracking are described. Results of calculations of residual stresses in core shroud weidments are summarized. Crack growth rates of high-nickel alloys under cyclic loading with R ratios from 0.2 to 0.95 in high-purity water that contains < 5 and 300 ppb dissolved oxygen at 240, 289, and 320C, are summarized. © 1999 Published by Elsevier Science S.A. All rights reserved.
  • Keywords
    Transient data collection , Pressurized water reactors , Fatigue monitoring
  • Journal title
    Nuclear Engineering and Design
  • Serial Year
    1999
  • Journal title
    Nuclear Engineering and Design
  • Record number

    14339