Corrosion fatigue initiation and short crack growth behaviour of austenitic stainless steels under light water reactor conditions

被引:42
|
作者
Seifert, H. P. [1 ]
Ritter, S. [1 ]
Leber, H. J. [1 ]
机构
[1] Paul Scherrer Inst, Nucl Energy & Safety Res Dept, Lab Nucl Mat, CH-5232 Villigen, Switzerland
关键词
Stainless steel; Corrosion fatigue; Reactor conditions; STRAIN STRESS;
D O I
10.1016/j.corsci.2012.02.008
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The corrosion fatigue initiation and short crack growth behaviour of different wrought low-carbon and stabilised austenitic stainless steels was characterised under simulated boiling water reactor and pressurised water reactor primary water conditions by cyclic fatigue tests with sharply notched fracture mechanics specimens. The special emphasis was placed to the behaviour at low corrosion potentials and, in particular, to hydrogen water chemistry conditions. The major parameter effects and critical conjoint threshold conditions, which result in relevant environmental reduction and acceleration of fatigue initiation life and subsequent short crack growth, respectively, are discussed and summarised. The observed corrosion fatigue behaviour is compared with the fatigue evaluation procedures in codes and regulatory guidelines. (C) 2012 Elsevier Ltd. All rights reserved.
引用
收藏
页码:20 / 34
页数:15
相关论文
共 50 条
  • [1] Corrosion fatigue crack growth behaviour of austenitic stainless steels under light water reactor conditions
    Seifert, H. P.
    Ritter, S.
    Leber, N. J.
    CORROSION SCIENCE, 2012, 55 : 61 - 75
  • [2] Fatigue crack initiation and propagation in austenitic stainless steels for light water reactors
    LeDuff, JA
    Ould, P
    Bernard, JL
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1996, 65 (03) : 241 - 253
  • [3] CORROSION-FATIGUE CRACK-GROWTH RATES IN AUSTENITIC STAINLESS-STEELS IN LIGHT WATER-REACTOR ENVIRONMENTS
    GILMAN, JD
    RUNGTA, R
    HINDS, P
    MINDLIN, H
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1988, 31 (01) : 55 - 68
  • [4] Corrosion fatigue crack growth behaviour of low-alloy reactor pressure vessel steels under boiling water reactor conditions
    Seifert, H. P.
    Ritter, S.
    CORROSION SCIENCE, 2008, 50 (07) : 1884 - 1899
  • [5] Corrosion fatigue crack initiation behavior of stainless steels
    Ebara, Ryuichiro
    FATIGUE 2010, 2010, 2 (01): : 1297 - 1306
  • [6] A FATIGUE CRACK GROWTH MODEL FOR TYPE 304 AUSTENITIC STAINLESS STEELS IN A PRESSURIZED WATER REACTOR ENVIRONMENT
    Barron, Kathleen C.
    Paraventi, Denise J.
    PROCEEDINGS OF ASME 2021 PRESSURE VESSELS AND PIPING CONFERENCE (PVP2021), VOL 1, 2021,
  • [7] EFFECTS OF MATERIAL COMPOSITION ON CORROSION FATIGUE CRACK GROWTH OF AUSTENITIC STAINLESS STEELS IN HIGH TEMPERATURE WATER
    Platts, Norman
    Tice, David
    Mottershead, Kevin
    McIntyre, Laura
    Scenini, Fabio
    15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 2011, : 561 - 579
  • [8] Fatigue short crack behaviour in metastable austenitic stainless steels with different grain sizes
    Stolarz, J
    Baffie, N
    Magnin, T
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2001, 319 : 521 - 526
  • [9] Thermal fatigue crack growth in austenitic stainless steels
    Virkkunen, I
    Kemppainen, M
    Hänninen, H
    FATIGUE '99: PROCEEDINGS OF THE SEVENTH INTERNATIONAL FATIGUE CONGRESS, VOLS 1-4, 1999, : 2183 - 2188
  • [10] Crack initiation mechanisms for corrosion fatigue of austenitic stainless steel
    Qian, YR
    Cahoon, JR
    CORROSION, 1997, 53 (02) : 129 - 135