Abstract
A test program has been completed that re-examined the effect of load ratio, R, on fatigue crack growth rates (FCGRs) of austenitic stainless steel in 482 °F air and deaerated water. Data for the test program were collected at R between 0.1 and 0.95 and ΔK values between 2.5 and 50 ksi√in to ensure an overlapping dataset in R and ∆K. In contrast to the single Paris slope relationship in the ASME code, results from air tests revealed a three-regime curve across many R: a high ΔK regime similar to ASME, an intermediate ΔK regime with a decreased power law exponent and a low ΔK region where FCGR exhibit a steep downturn. Water FCGRs showed two regimes—a single power law regime and a steep low ΔK regime. FCGR sensitivity to R was greatest in the low ΔK regime for both environments.
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References
L.A. James, D.P. Jones, Fatigue Crack Growth Correlations for Austenitic Stainless Steels in Air. Predict. Capab. Environ. Assist. Crack. ASME PVP 99, 363–414 (1985)
ASME Pressure Vessel and Piping Code, Section XI, Division 1, Appendix C, Section C-8400, Fatigue Crack Growth Rate, 2007, pp. 381–383
G.L. Wire, W.J. Mills, in Pressure vessel and piping codes and standards—2002, ASME PVP-Vol. 439, 2002, pp. 151–164
W.M. Evans, G.L. Wire, in Pressure vessel and piping codes and standards—2002, ASME PVP-Vol. 439, 2002, pp. 91–98
G.L. Wire, W.M. Evans, W.J. Mills, in Pressure vessel and piping codes and standards—2004, ASME PVP-Vol. 480, 2004, PVP2004-2675, pp. 151–164
G.L. Wire, W.M. Evans, W.J. Mills, in Pressure Vessel and Piping Codes and Standards—2005, 2005, PVP2005-71608
D.R. Tice, K.M.S. Rigby, D.I. Swan, Corrosion fatigue crack growth of austenitic stainless steel in PWR primary coolant at low frequency, in Proceedings of the Third International Conference on Fatigue of Reactor Components, Seville, Spain, Oct 2004
D. Tice, N. Platts, K. Rigby, J. Stairmand, D. Swan, Influence of PWR primary coolant environment on corrosion fatigue crack growth of austenitic stainless steel, in Pressure Vessel and Piping Codes and Standards—2005, 2005, PVP2005-71563
D.R. Tice, N. Platts, K. Rigby, J.W. Stairmand, Influence of temperature and flow rate on the corrosion fatigue crack growth of austenitic stainless steels in a PWR primary coolant environment, in 13th International Conference on Environmental Degradation in Nuclear Power Systems, Whistler, British Columbia, Canada, Aug 2007
N. Platts, D.R. Tice, J.W. Stairmand, Effect of flow rate on teh environmentally enhanced fatigue crack propagation of austenitic stainless steels in a simulated PWR primary coolant environment, in 14th International Conference on Environmental Degradation in Nuclear Power Systems, Virginia Beach, VA, Aug 2009
Y. Nomura, K. Tsutsumi, H. Kanasaki, N. Chigusa, K. Jotaki, H. Shimizu, T. Hirose, H. Ohata, PVP-Vol. 480, Pressure Vessel and Piping Codes and Standards–2004, ASME PVP2004-2674, 2004, pp. 63–70
Y. Nomura, K. Sakaguchi, H. Kanasaki, S. Suzuki, in 2006 ASME Pressure Vessels and Piping Division Conference, 2006, PVP2006-ICPVT-11-93224
J.L. Bernard, G. Slama, C. Amzallag, P. Rabbe, Meeting on Time and Load Dependent Degradation of Pressure Boundary Materials, IWG-RRPC-79/2, 1979, IAEA, pp. 27–36
P.L. Andresen, C.L. Briant, Corrosion (1989), pp. 448–463
L.G. Ljunberg, D. Cubicciotti, M. Trolle, in Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 1990, NACE, pp. 459–475
W.J. Mills, Critical review of fatigue crack growth rates for stainless steel in deaerated water, in Presented at the EPRI Materials Reliability Program Conference, Session 9a, Colorado Springs, 28 June–1 July 2010
R.C. Cipolla, W.H. Bamford, Technical basis for code case N-809 on reference fatigue crack growth curves for austenitic stainless steels in pressurized water reactor environments, in ASME Pressure Vessel and Piping Conference—PVP 2015-45884, July 2015
K.H. Schwalbe, D. Hellmann, Application of the electrical potential method to crack length measurements using Johnson’s formula. J. Test. Eval. 9, 218 (1981)
J.K. Donald, J. Ruschau, Direct current potential difference fatigue crack measurement techniques, in Fatigue Crack Measurement: Techniques and Applications, EMAS, 1991, p. 11
L.B. O’Brien, R.G. Ballinger, D.J. Paraventi, L. Yn, Y. Maruno, P.W. Stahle, The effect of environment, chemistry, and microstructure on the corrosion fatigue behavior of austenitic stainless steels in high temperature water, in 17th International Conference on Environmental Degradation in Nuclear Power Systems, 9–13 Aug 2015, Ottawa, Ontario, Canada
E.A. West, H.M. Mohr, E. Lord, Fatigue threshold behavior of stainless steel in high temperature air and water, in Proceedings of the ASME 2016 Pressure Vessels & Piping Conference, PVP2016, 17–21 July 2016, Vancouver, BC, Canada, PVP2016-63051
W.J. Mills, Accelerated and retarded corrosion fatigue crack growth rates for 304 stainless steel in an elevated temperature aqueous environment, in 16th International Conference on Environmental Degradation in Nuclear Power Systems, Asheville, NC, Aug 2013
Acknowledgements
The following organizations and their staff (past and present) are gratefully acknowledged: Naval Nuclear Laboratory—Bettis Advanced Materials Testing Laboratory, Mechanical Testing, and Welding Laboratory. This work is the result of the efforts started by and the insight of the late Dr. William J. Mills.
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Paraventi, D.J., Brown, C.M., O’Brien, L.B., McGraw, B.A. (2019). The Effect of Load Ratio on the Fatigue Crack Growth Rate of Type 304 Stainless Steels in Air and High Temperature Deaerated Water at 482 °F. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_57
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