Fatigue tests have been conducted on Types 304 and 316NG stainless steels to evaluate the effects of various material and loading variables, e.g., steel type, strain rate, dissolved oxygen (DO) in water, and strain range, on the fatigue lives of these steels. The results confirm significant decreases in fatigue life in water. Unlike the situation with ferritic steels, environmental effects on Types 304 and 316NG stainless steel are more pronounced in low-DO than in high-DO water. Experimental results have been compared with estimates of fatigue life based on a statistical model. The formation and growth of fatigue cracks in air and water environments are discussed.
Issue Section:
Research Papers
1.
Chopra
O. K.
Shack
W. J.
1995
, “Effects of LWR Environments on Fatigue Life of Carbon and Low-Alloy Steels
,” Fatigue and Crack Growth: Environmental Effects, Modeling Studies, and Design Considerations, ASME PVP
-Vol. 306
, S. Yukawa, ed., American Society of Mechanical Engineers, New York, NY, pp. 95
–109
.2.
Chopra, O. K., and Shack, W. J., 1997, “Evaluation of Effects of LWR Coolant Environments on Fatigue Life of Carbon and Low-Alloy Steels,” Proceedings of Symposium on Effects of the Environment on the Initiation of Crack Growth, ASTM STP 1298, American Society for Testing and Materials, Philadelphia, PA, pp. 247–266.
3.
Conway, J. B., Stentz, R. H., and Berling, J. T., 1975, Fatigue, Tensile, and Relaxation Behavior of Stainless Steels, TID-26135, U.S. Atomic Energy Commission, Washington, DC.
4.
Ford, F. P., Ranganath, S., and Weinstein, D., 1993, Environmentally Assisted Fatigue Crack Initiation in Low-Alloy Steels—A Review of the Literature and the ASME Code Design Requirements, EPRI Report TR-102765.
5.
Hale, D. A., Wilson, S. A., Kiss, E., and Gianuzzi, A. J., 1977, Low Cycle Fatigue Evaluation of Primary Piping Materials in a BWR Environment, GEAP-20244, U.S. Nuclear Regulatory Commission.
6.
Hale
D. A.
Wilson
S. A.
Kass
J. N.
Kiss
E.
1981
, “Low Cycle Fatigue Behavior of Commercial Piping Materials in a BWR Environment
,” ASME Journal of Engineering Material Technology
, Vol. 103
, pp. 15
–25
.7.
Ha¨nninen, H., To¨rro¨nen, K., and Cullen, W. H., 1986, “Comparison of Proposed Cyclic Crack Growth Mechanisms of Low Alloy Steels in LWR Environments,” Proceedings 2nd International Atomic Energy Agency Specialists’ Meeting on Subcritical Crack Growth, NUREG/CP-0067, MEA-2090, Vol. 2, pp. 73–97.
8.
Higuchi, M., 1992, Ishikawijima-Harima Heavy Industries Co., Japan, private communication to M. Prager, Pressure Vessel Research Council, New York, NY.
9.
Higuchi
M.
Iida
K.
1991
, “Fatigue Strength Correction Factors for Carbon and Low-Alloy Steels in Oxygen-Containing High-Temperature Water
,” Nuclear Engineering Design
, Vol. 129
, pp. 293
–306
.10.
Higuchi
M.
Iida
K.
Asada
Y.
1995
, “Effects of Strain Rate Change on Fatigue Life of Carbon Steel in High-Temperature Water
,” Fatigue and Crack Growth: Environmental Effects, Modeling Studies, and Design Considerations, ASME PVP
-Vol. 306
, S. Yukawa, ed., American Society of Mechanical Engineers, New York, NY, pp. 111
–116
.11.
Jaske
C. E.
O’Donnell
W. J.
1977
, “Fatigue Design Criteria for Pressure Vessel Alloys
,” ASME JOURNAL OF PRESSURE VESSEL TECHNOLOGY
, Vol. 99
, pp. 584
–592
.12.
Keisler, J., Chopra, O. K., and Shack, W. J., 1995, Fatigue Strain-Life Behavior of Carbon and Low-Alloy Steels, Austenitic Stainless Steels, and Alloy 600 in LWR Environments, NUREG/CR-6335, ANL-95/15.
13.
Keisler
J. M.
Chopra
O. K.
Shack
W. J.
1996
, “Fatigue Strain-Life Behavior of Carbon and Low-Alloy Steels, Austenitic Stainless Steels, and Alloy 600 in LWR Environments
,” Nuclear Engineering Design
, Vol. 167
, pp. 129
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.14.
Keller, D. L., 1977, Progress on LMFBR Cladding, Structural, and Component Materials Studies During July, 1971 through June, 1972, Final Report, Task 32, Battelle-Columbus Laboratories, BMI-1928.
15.
Majumdar, S., Chopra, O. K., and Shack, W. J., 1993, Interim Fatigue Design Curves for Carbon, Low-Alloy, and Austenitic Stainless Steels in LWR Environments, NUREG/CR-5999, ANL-93/3.
16.
Mimaki
H.
Kanasaki
H.
Suzuki
I.
Koyama
M.
Akiyama
M.
Okubo
T.
Mishima
Y.
1996
, “Material Aging Research Program for PWR Plants
,” Aging Management Through Maintenance Management, ASME PVP
-Vol. 332
, I. T. Kisisel, ed., American Society of Mechanical Engineers, New York, NY, pp. 97
–105
.17.
Shack, W. J., and Burke, W. F., 1991, “Fatigue of Type 316NG SS,” Environmentally Assisted Cracking in Light Water Reactors, Semiannual Report, October 1989–March 1990, NUREG/CR-4667 Vol. 10, ANL-91/5, pp. 3–19.
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