Fatigue crack-growth behavior was investigated for types 304 and 316 stainless steel exposed to a pressurized water reactor environment. The effects of test frequency, stress ratio, specimen orientation, heat to heat variables and weld versus base metal performance were evaluated. Crack-growth rates were correlated with the range of crack-tip stress intensity factor, as well as the “effective stress intensity factor” proposed by Walker to account for R ratio effects. Results of the study showed that fatigue crack-growth rates in the water environment were not significantly different from results at the same stress ratio in an air environment at the same temperature. The most important parameter found to affect the crack-growth rate was the stress ratio R, and increasing values of R produced increased crack-growth rates at any given value of stress intensity factor range ΔK. The stress ratio effects were successfully accounted for by employment of the Walker model.
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February 1979
Research Papers
Fatigue Crack Growth of Stainless Steel Piping in a Pressurized Water Reactor Environment
W. H. Bamford
W. H. Bamford
Westinghouse Nuclear Energy Systems, Pittsburgh, Pa. 15230
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W. H. Bamford
Westinghouse Nuclear Energy Systems, Pittsburgh, Pa. 15230
J. Pressure Vessel Technol. Feb 1979, 101(1): 73-79 (7 pages)
Published Online: February 1, 1979
Article history
Received:
June 3, 1977
Online:
October 25, 2010
Citation
Bamford, W. H. (February 1, 1979). "Fatigue Crack Growth of Stainless Steel Piping in a Pressurized Water Reactor Environment." ASME. J. Pressure Vessel Technol. February 1979; 101(1): 73–79. https://doi.org/10.1115/1.3454601
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