The fatigue crack growth behavior of sensitized Type 304 (UNS S30400) stainless steel (SS) with an electrochemical potentiokinetic reactivation (EPR) value of 30 C/cm2 was investigated under boiling water reactor (BWR) conditions at 288°C. Tests were performed under either cyclic or trapezoidal loading conditions. Test environments were high-purity water either with 200 ppb dissolved oxygen (DO) under normal water chemistry (NWC) conditions or with 10 ppb DO plus 160 ppb dissolved hydrogen (DH) under hydrogen water chemistry (HWC) conditions. It was observed that whether the loading waveform was cyclic or trapezoidal, the fatigue crack growth rates (FCGR) could not be reduced by HWC conditions. None of the current FCGR data was encompassed by the reference curves of the ASME Code Section XI, Appendix C (ASME-XI, Appendix C), whereas all of the current data could be bounded by the JSME flaw evaluation code (JSME S NA1-2000). Finally, the examination of the accuracy of the superposition principles indicated that the Argonne National Laboratory (ANL) model was higher than that developed by the General Electric (GE) model.
Skip Nav Destination
Article navigation
1 November 2007
Research Article|
November 01 2007
Fatigue Crack Growth Behavior of Sensitized Type 304 Stainless Steel Under Boiling Water Reactor Conditions
Y.Y. Chen;
Y.Y. Chen
‡
*Department of Materials Science and Engineering, National Tsing Hua University, Hsinchu, Taiwan 300,
R.O.C.
‡Corresponding author. E-mail: [email protected].
Search for other works by this author on:
H.C. Shih;
H.C. Shih
*Department of Materials Science and Engineering, National Tsing Hua University, Hsinchu, Taiwan 300,
R.O.C.
Search for other works by this author on:
L.H. Wang;
L.H. Wang
**Materials Research Laboratories, Industrial Technology Research Institute, Hsinchu, Taiwan 310,
R.O.C.
Search for other works by this author on:
J.C. Oung
J.C. Oung
**Materials Research Laboratories, Industrial Technology Research Institute, Hsinchu, Taiwan 310,
R.O.C.
Search for other works by this author on:
‡Corresponding author. E-mail: [email protected].
Online ISSN: 1938-159X
Print ISSN: 0010-9312
NACE International
2007
CORROSION (2007) 63 (11): 997–1008.
Citation
Y.Y. Chen, H.C. Shih, L.H. Wang, J.C. Oung; Fatigue Crack Growth Behavior of Sensitized Type 304 Stainless Steel Under Boiling Water Reactor Conditions. CORROSION 1 November 2007; 63 (11): 997–1008. https://doi.org/10.5006/1.3278324
Download citation file:
Citing articles via
Suggested Reading
Characterization of the Oxide Film Formed on Type 316 Stainless Steel in 288°C Water in Cyclic Normal and Hydrogen Water Chemistries
CORROSION (November,1995)
Viability of Hydrogen Water Chemistry for Protecting In-Vessel Components of Boiling Water Reactors
CORROSION (March,1992)