Fatigue crack growth behavior of sensitized type 304 stainless steel under boiling water reactor conditions

The fatigue crack growth behavior of sensitized Type 304 (UNS S30400) stainless steel (SS) with an electrochemical potentiokinetic reactivation (EPR) value of 30 C/cm(2) was investigated under boiling water reactor (BWR) conditions at 288 degrees 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 non-nal water chemistry (NWC) conditions or with 10 ppb DO plus 160 ppb dissolved hydrogen (DH) under hydrogen water chemistry (HWQ conditions. It was observed that whether the loading waveform was cyclic or trapezoidal, thefatigue crack growth rates (F)CGR) could not be reduced by HWC conditions. None of the current PCGR data was encompassed by the reference curves of the ASME Code Section X1, Appendix C (ASME-XI, Appendix C), whereas all of the current data could be bounded by theJSMEflaw evaluation code (JSME S NA1-2000). Mnally, 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.