Models of fatigue crack growth rates for medium and low sulfur ferritic pressure vessel steels in pressurized water reactor (PWR) primary environments are developed based on a recent collection of UK data and the EPRI Database for Environmentally Assisted Cracking (EDEAC). The combined UK and EDEAC database contains a broader range of experimental conditions specific to PWRs than either database by itself. Both probabilistic and conventional crack growth rate models are developed that reduce unnecessary conservatism for medium and low sulfur PWR primary water applications and eliminate the explicit dependence on rise time that caused difficulties applying prior models.
Issue Section:
Technical Papers
1.
Eason, E. D., and Nelson, E. E., 1999, “Analysis of the UK Corrosion Fatigue Crack Growth Database,” Proprietary, Limited Distribution Report 990501, Modeling & Computing Services, Boulder, CO.
2.
Eason, E. D., and Nelson, E. E., 1993, “Analysis of Fatigue Crack Growth Rate Data for A508 and A533 Steels in LWR Environments,” Report TR-102793, EPRI, Palo Alto, CA.
3.
Eason
, E. D.
, Nelson
, E. E.
, and Gilman
, J. D.
, 1998
, “Modeling of Fatigue Crack Growth Rate for Ferritic Steels in Light Water Reactor Environments
,” Nucl. Eng. Des.
, 184
, pp. 89
–111
.4.
Eason
, E. D.
, Nelson
, E. E.
, and Gilman
, J. D.
, 1995
, “Technical Basis for a Revised Fatigue Crack Growth Rate Reference Curve for Ferritic Steels in Light Water Reactor Environments
,” Weld. Res. Counc. Bull.
, 404
, pp. 38
–51
.5.
Eason
, E. D.
, Gilman
, J. D.
, Jones
, D. P.
, and Andrew
, S. P.
, 1992
, “Technical Basis for a Revised Fatigue Crack Growth Rate Curve for Ferritic Steels in Air
,” ASME J. Pressure Vessel Technol.
, 114
, pp. 80
–86
.6.
James
, L. A.
, 1995
, “Environmentally-Assisted Cracking of Ferritic Steels in Aqueous Environments: An Interpretive Review
,” Weld. Res. Counc. Bull.
, 404
, pp. 1
–20
.7.
Special Issue on the ICCGR, 1989, International Journal of Pressure Vessels and Piping, 40(5).
8.
ASME, 1986, “Rules for Inservice Inspection of Nuclear Power Plant Components,” ASME Boiler and Pressure Vessel Code, Section XI.
9.
Bamford
, W. H.
, 1980
, “Technical Basis for Revised Crack Growth Rate Curves for Pressure Boundary Steels in LWR Environment
,” ASME J. Pressure Vessel Technol.
, 102
, pp. 433
–442
.10.
Mindlin, H., et al., 1986, “EPRI Database for Environmentally Assisted Cracking (EDEAC),” Report NP-4485, EPRI, Palo Alto, CA.
11.
Case N-643, 2000, “Fatigue Crack Growth Rate Curves for Ferritic Steels in PWR Water Environment,” Section XI, Division 1, ASME Boiler and Pressure Vessel Code, ASME, New York.
12.
Atkinson, J. D., Scott, P. M., and Tice, D. R., 1989, “A Review of Fatigue Crack Propagation Laws for Use in Assessments of Ferritic Steel PWR Pressure Vessels,” Memorandum ESTD/L/SAD/0014/M89, National Power, UK.
13.
Scott
, P. M.
, and Truswell
, A. E.
, 1983
, “Corrosion Fatigue Crack Growth in Reactor Pressure Vessel Steels in PWR Primary Water
,” ASME J. Pressure Vessel Technol.
, 105
, pp. 245
–254
.14.
Bamford, W. H., 1988, “A Summary of Environmentally Assisted Crack Growth Studies Performed at Westinghouse Electric Corporation: Under Funding from the Heavy Section Steel Technology Program,” NUREG/CR-5020, Nuclear Regulatory Commission, Washington D.C.
15.
Van der Sluys, W. A., and Emanuelson, R. H., 1990, “Environmental Acceleration of Fatigue Crack Growth in Reactor Pressure Vessel Materials and Environments,” Environmentally Assisted Cracking: Science and Engineering, W. B. Lisagor, T. W. Crooker, and B. N. Leis, eds., ASTM, Philadelphia, STP 1049, pp. 117–135.
16.
Eason, E. D., Warmbrodt, S. B., Andrew, S. P., and Nelson, E. E., 1993, “FATDAC—Fatigue Data Analysis Code,” Report TR-102795, EPRI, Palo Alto, CA.
17.
Andrew, S. P., Eason, E. D., and Warmbrodt, S. B., 1992, “The FATDAC Code for Fatigue Data Analysis,” Computerization and Networking of Materials Databases: Third Volume, K. W. Reynard and T. I. Barry, eds., ASTM, Philadelphia, STP 1140, pp. 388–394.
18.
Clark, W. G., Jr., and Hudak, S. J. Jr., 1975, “Variability in Fatigue Crack Growth Rate Testing,” J. Testing and Evaluation, 3(6), pp. 454–476.
19.
Shoji, T., and Takahashi, H., 1983, “Role of Loading Variables in Environment Enhanced Crack Growth for Water-Cooled Nuclear Reactor Pressure Vessels,” Proc. IAEA Specialist Meeting on Subcritical Crack Growth, NUREG/CP-0044, Vol. 2, Nuclear Regulatory Commission, Washington D.C., pp. 143–171.
20.
Shoji
, T.
, Takahashi
, H.
, Suzuki
, M.
, and Kondo
, T.
, 1981
, “A New Parameter for Characterizing Corrosion Fatigue Crack Growth
,” ASME J. Eng. Mater. Technol.
, 103
, pp. 298
–304
.21.
Ford
, F. P.
, 1988
, “Status of Research on Environmentally Assisted Cracking in LWR Pressure Vessel Steels
,” ASME J. Pressure Vessel Technol.
, 110
, pp. 113
–128
.22.
Ford, F. P., Taylor, D. F., Andresen, P. L., and Ballinger, R. G., 1987, “Corrosion-Assisted Cracking of Stainless and Low-Alloy Steels in LWR Environments,” Report NP-5064N, EPRI, Palo Alto, CA.
23.
Wire, G. L., and Kandra, J. T., 1997, “Threshold Velocity for Environmentally-Assisted Cracking in Low Alloy Steels,” 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, American Nuclear Society, La Grange Park, IL, pp. 932–940.
24.
James, L. A., 1998, “Technical Basis for the Initiation and Cessation of Environmentally-Assisted Cracking of Low-Alloy Steels in Elevated Temperature PWR Environments,” Fatigue, Environmental Factors, and New Materials, H. S. Mehta, ed., ASME, New York, PVP Vol. 374, pp. 207–230.
25.
Wire
, G. L.
, 2000
, “Cessation of Environmentally-Assisted Cracking in a Low-Alloy Steel: Theoretical Analysis
,” Nucl. Eng. Des.
, 197
, pp. 25
–44
.26.
Yin Li
, Y.
, 2000
, “Cessation of Environmentally-Assisted Cracking in a Low-Alloy Steel: Experimental Results
,” Nucl. Eng. Des.
, 197
, pp. 45
–60
.27.
Ruther, W. E. et al., 1991, “Environmentally Assisted Cracking in Light Water Reactors,” NUREG/CR-4667, Vol. 10, Nuclear Regulatory Commission, Washington D.C.
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