Development of fatigue design curve for austenitic stainless steels in LWR environments: A review

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 439, Issue , 2002, Pages 119-132

  Chopra, Omesh K ^a  

^a ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

STRAIN AMPLITUDES;

AUSTENITE; COOLANTS; DATA ACQUISITION; FATIGUE OF MATERIALS; LIGHT WATER REACTORS; NUCLEAR POWER PLANTS; PARAMETER ESTIMATION; PRESSURE VESSEL CODES; STEEL PIPE; STRAIN RATE;

STAINLESS STEEL;

EID: 0036384784     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2002-1229     Document Type: Conference Paper

References (66)

1. K. Kussmaul, R. Rintamaa, J. Jansky, M. Kemppainen, and K. Törrönen, On the Mechanism of Environmental Cracking Introduced by Cyclic Thermal Loading, in IAEA Specialists Meeting Corrosion and Stress Corrosion of Steel Pressure Boundary Components and Steam Turbines, VTT Symp. 43, Espoo, Finland, pp. 195-243 (1983).
2. K. Iida, A Review of Fatigue Failures in LWR Plants in Japan, Nucl. Eng. Des. 138, 297-312 (1992).
3. NRC IE Bulletin No. 79-13, Cracking in Feedwater System Piping, U.S. Nuclear Regulatory Commission, Washington, DC (June 25, 1979).
4. NRC Information Notice 93-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators, U.S. Nuclear Regulatory Commission, Washington, DC (March 24, 1993).
5. K. Kussmaul, D. Blind, and J. Jansky, Formation and Growth of Cracking in Feed Water Pipes and RPV Nozzles, Nucl. Eng. Des. 81, 105-119 (1984).
6. H. Watanabe, Boiling Water Reactor Feedwater Nozzle/Sparger, Final Report, NEDO-21821-A, General Electric Co., San Jose, CA, (1980).
7. B.M. Gordon, D.E. Delwiche, and G.M. Gordon, Service Experience of BWR Pressure Vessels, in Performance and Evaluation of Light Water Reactor Pressure Vessels, PVP Vol.-119, American Society of Mechanical Engineers, New York, pp. 9-17 (1987).
8. E. Lenz, B. Stellwag, and N. Wieling, The Influence of Strain-Induced Corrosion Cracking on the Crack Initiation in Low-Alloy Steels in HT-Water - A Relation Between Monotonic and Cyclic Crack Initiation Behavior, in IAEA Specialists Meeting Corrosion and Stress Corrosion of Steel Pressure Boundary Components and Steam Turbines, VTT Symp. 43, Espoo, Finland, pp. 243-267 (1983).
9. J. Hickling and D. Blind, Strain-Induced Corrosion Cracking of Low-Alloy Steels in LWR Systems - Case Histories and Identification of Conditions Leading to Susceptibility, Nucl. Eng. Des. 91, 305-330 (1986).
10. P. Hirschberg, A.F. Deardorff, and J. Carey, Operating Experience Regarding Thermal Fatigue of Unisolable Piping Connected to PWR Reactor Coolant Systems, Int. Conf. on Fatigue of Reactor Components, Napa, CA, July 31-August 2, 2000.
11. NRC Information Notice 88-01, Safety Injection Pipe Failure, U.S. Nuclear Regulatory Commission, Washington, DC (Jan. 27, 1988).
12. NRC Bulletin No. 88-08, Thermal Stresses in Piping Connected to Reactor Coolant Systems, U.S. Nuclear Regulatory Commission, Washington, DC (June 22; Suppl. 1, June 24; Suppl. 2, Aug. 4, 1988; Suppl. 3, April 1989).
13. R.B. Dooley, and R.S. Pathania, Corrosion Fatigue of Water Touched Pressure Retaining Components in Power Plants, EPRI TR-106696, Electric Power Research Institute, Palo Alto, CA (1997).
14. V.N. Shah, M.B. Sattison, C.L. Atwood, A.G. Ware, G.M. Grant, and R.S. Hartley, Assessment of Pressurized Water Reactor Primary System Leaks, NUREG/CR-6582, INEEL/EXT-97-01068 (Dec. 1998).
15. C.E. Jaske and W.J. O'Donnell, Fatigue Design Criteria for Pressure Vessel Alloys, Trans. ASME J. Pressure Vessel Technol. 99, 584-592 (1977).
16. O.K. Chopra, Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels, NUREG/CR-5704, ANL-98/31 (1999).
17. O.K. Chopra and W.J. Shack, Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels, NUREG/CR-6583, ANL-97/18 (March 1998).
18. O.K. Chopra and W.J. Shack, Environmental Effects on Fatigue Crack Initiation in Piping and Pressure Vessel Steels, NUREG/CR-6717, ANL-00/27 (May 2001).
19. S. Majumdar, O.K. Chopra, and W.J. Shack, Interim Fatigue Design Curves for Carbon, Low-Alloy, and Austenitic Stainless Steels in LWR Environments, NUREG/CR-5999, ANL-93/3 (1993).
20. J. Keisler, O.K. Chopra, and W.J. Shack, 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 (1995).
21. J. Keisler, O.K. Chopra, and W.J. Shack, Statistical Models for Estimating Fatigue Strain-Life Behavior of Pressure Boundary Materials in Light Water Reactor Environments, Nucl. Eng. Des. 167, 129-154 (1996).
22. M. Higuchi and K. Iida, Fatigue Strength Correction Factors for Carbon and Low-Alloy Steels in Oxygen-Containing High-Temperature Water, Nucl. Eng. Des. 129, 293-306 (1991).
23. H.S. Mehta and S.R. Gosselin, An Environmental Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel and Piping Fatigue Evaluations, in Fatigue and Fracture Volume 1, PVP Vol. 323, H.S. Mehta, ed., American Society of Mechanical Engineers, New York, pp. 171-185 (1996).
24. H.S. Mehta and S.R. Gosselin, Environmental Factor Approach to Account for Water Effects in Pressure Vessel and Piping Fatigue Evaluations, Nucl. Eng. Des. 181, 175-197 (1998).
25. H.S. Mehta, An Update on the EPRI/GE Environmental Fatigue Evaluation Methodology and its Applications, in Probabilistic and Environmental Aspects of Fracture and Fatigue, PVP Vol. 386, S. Rahman, ed., American Society of Mechanical Engineers, New York, pp. 183-193 (1999).
26. K. Iida, T. Bannai, M. Higuchi, K. Tsutsumi, and K. Sakaguchi, Comparison of Japanese MITI Guideline and Other Methods for Evaluation of Environmental Fatigue Life Reduction, in Pressure Vessel and Piping Codes and Standards, PVP Vol. 419, M.D. Rana, ed., American Society of Mechanical Engineers, New York, pp. 73-81 (2001).
27. J.B. Conway, R.H. Stentz, and J.T. Berling, Fatigue, Tensile, and Relaxation Behavior of Stainless Steels, TID-26135, U.S. Atomic Energy Commission, Washington, DC (1975).
28. D.L. Keller, Progress on LMFBR Cladding, Structural, and Component Materials Studies During July, 1971 through June, 1972, Final Report, Task 32, BMI-1928, Battelle-Columbus Laboratories (1977).
29. D.A. Hale, S.A. Wilson, E. Kiss, and A.J. Gianuzzi, Low Cycle Fatigue Evaluation of Primary Piping Materials in a BWR Environment, GEAP-20244, U.S. Nuclear Regulatory Commission (Sept. 1977).
30. M. Fujiwara, T. Endo, and H. Kanasaki, Strain Rate Effects on the Low-Cycle Fatigue Strength of 304 Stainless Steel in High-Temperature Water Environment; Fatigue Life: Analysis and Prediction, in Proc. Intl. Conf. and Exposition on Fatigue, Corrosion Cracking, Fracture Mechanics, and Failure Analysis, ASM, Metals Park, OH, pp. 309-313 (1986).
31. H. Mimaki, H. Kanasaki, I. Suzuki, M. Koyama, M. Akiyama, T. Okubo, and Y. Mishima, Material Aging Research Program for PWR Plants, in Aging Management Through Maintenance Management, PVP Vol. 332, I.T. Kisisel, ed., American Society of Mechanical Engineers, New York, pp. 97-105 (1996).
32. H. Kanasaki, R. Umehara, H. Mizuta, and T. Suyama, Fatigue Lives of Stainless Steels in PWR Primary Water, Trans. 14th Intl. Conf. on Structural Mechanics in Reactor Technology (SMiRT 14), Lyon, France, pp. 473-483 (1997).
33. H. Kanasaki, R. Umehara, H. Mizuta, and T. Suyama, Effects of Strain Rate and Temperature Change on the Fatigue Life of Stainless Steel in PWR Primary Water, Trans. 14th Intl. Conf. on Structural Mechanics in Reactor Technology (SMiRT 14), Lyon, France, pp. 485-493 (1997).
34. K. Tsutsumi, H. Kanasaki, T. Umakoshi, T. Nakamura, S. Urata, H. Mizuta, and S. Nomoto, Fatigue Life Reduction in PWR Water Environment for Stainless Steels, in Assessment Methodologies for Preventing Failure: Service Experience and Environmental Considerations, PVP Vol. 410-2, R. Mohan, ed., American Society of Mechanical Engineers, New York, pp. 23-34 (2000).
35. K. Tsutsumi, T. Dodo, H. Kanasaki, S. Nomoto, Y. Minami, and T. Nakamura, Fatigue Behavior of Stainless Steel under Conditions of Changing Strain Rate in PWR Primary Water, in Pressure Vessel and Piping Codes and Standards, PVP Vol. 419, M.D. Rana, ed., American Society of Mechanical Engineers, New York, pp. 135-141 (2001).
36. M. Higuchi and K. Iida, Reduction in Low-Cycle Fatigue Life of Austenitic Stainless Steels in High-Temperature Water, in Pressure Vessel and Piping Codes and Standards, PVP Vol. 353, D.P. Jones, B.R. Newton, W.J. O'Donnell, R. Vecchio, G.A. Antaki, D. Bhavani, N.G. Cofie, and G.L. Hollinger, eds., American Society of Mechanical Engineers, New York, pp. 79-86 (1997).
37. M. Higuchi, K. Iida, and K. Sakaguchi, Effects of Strain Rate Fluctuation and Strain Holding on Fatigue Life Reduction for LWR Structural Steels in Simulated PWR Water, in Pressure Vessel and Piping Codes and Standards, PVP Vol. 419, M.D. Rana, ed., American Society of Mechanical Engineers, New York, pp. 143-152 (2001).
38. M. Hayashi, Thermal Fatigue Strength of Type 304 Stainless Steel in Simulated BWR Environment, Nucl. Eng. Des. 184, 135-144 (1998).
39. M. Hayashi, K. Enomoto, T. Saito, and T. Miyagawa, Development of Thermal Fatigue Testing with BWR Water Environment and Thermal Fatigue Strength of Austenitic Stainless Steels, Nucl. Eng. Des. 184, 113-122 (1998).
40. O.K. Chopra and D.J. Gavenda, Effects of LWR Coolant Environments on Fatigue Lives of Austenitic Stainless Steels, in Pressure Vessel and Piping Codes and Standards, PVP Vol. 353, D.P. Jones, B.R. Newton, W.J. O'Donnell, R. Vecchio, G.A. Antaki, D. Bhavani, N.G. Cofie, and G.L. Hollinger, eds., American Society of Mechanical Engineers, New York, pp. 87-97 (1997).
41. O.K. Chopra and D.J. Gavenda, Effects of LWR Coolant Environments on Fatigue Lives of Austenitic Stainless Steels, J. Pressure Vessel Technol. 120, 116-121 (1998).
42. O.K. Chopra and J.L. Smith, Estimation of Fatigue Strain-Life Curves for Austenitic Stainless Steels in Light Water Reactor Environments, in Fatigue, Environmental Factors, and New Materials, PVP Vol. 374, H.S. Mehta, R.W. Swindeman, J.A. Todd, S. Yukawa, M. Zako, W.H. Bamford, M. Higuchi, E. Jones, H. Nickel, and S. Rahman, eds., American Society of Mechanical Engineers, New York, pp. 249-259 (1998).
43. O.K. Chopra and J. Muscara, Effects of Light Water Reactor Coolant Environments on Fatigue Crack Initiation in Piping and Pressure Vessel Steels, in Proc. 8th Intl. Conf. on Nuclear Engineering, 2.08 LWR Materials Issue, Paper 8300, American Society of Mechanical Engineers, New York (2000).
44. C. Amzallag, P. Rabbe, G. Gallet, H.-P. Lieurade, Influence des Conditions de Sollicitation Sur le Comportement en Fatigue Oligocyclique D'aciers Inoxydables Austénitiques, Memoires Scientifiques Revue Metallurgie Mars, pp. 161-173 (1978).
45. A. Hirano, M. Yamamoto, K. Sakaguchi, K. Iida, and T. Shoji, Effects of Water Flow Rate on Fatigue Life of Carbon Steel in High-Temperature Pure Water Environment, in Assessment Methodologies for Predicting Failure: Service Experience and Environmental Considerations, PVP Vol. 410-2, R. Mohan, ed., American Society of Mechanical Engineers, New York, pp. 13-18 (2000).
46. E. Lenz, N. Wieling, and H. Muenster, Influence of Variation of Flow Rates and Temperature on the Cyclic Crack Growth Rate under BWR Conditions, in Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, The Metallurgical Society, Warrendale, PA (1988).
47. B.F. Langer, Design of Pressure Vessels for Low-Cycle Fatigue, ASME J. Basic Eng. 84, 389-402 (1962).
48. T.R. Leax, Statistical Models of Mean Stress and Water Environment Effects on the Fatigue Behavior of 304 Stainless Steel, in Probabilistic and Environmental Aspects of Fracture and Fatigues, PVP Vol. 386, S. Rahman, ed., American Society of Mechanical Engineers, New York, pp. 229-239 (1999).
49. K.N. Smith, P. Watson, and T.H. Topper, A Stress-Strain Function for the Fatigue of Metals, J. Mater., JMLSA 5 (4), 767-778 (1970).
50. G.L. Wire, T.R. Leax, and J.T. Kandra, Mean Stress and Environmental Effects on Fatigue in Type 304 Stainless Steel, in Probabilistic and Environmental Aspects of Fracture and Fatigues, PVP Vol. 386, S. Rahman, ed., American Society of Mechanical Engineers, New York, pp. 213-228 (1999).
51. M.E. Mayfield, E.C. Rodabaugh, and R.J. Eiber, A Comparison of Fatigue Test Data on Piping with the ASME Code Fatigue Evaluation Procedure, ASME Paper 79-PVP-92, American Society of Mechanical Engineers, New York (1979).
52. A.F. Deardorff and J.K. Smith, Evaluation of Conservatisms and Environmental Effects in ASME Code, Section III, Class 1 Fatigue Analysis, SAND94-0187, prepared by Structural Integrity Associates, San Jose, CA, under contract to Sandia National Laboratories, Albuquerque, NM (1994).
53. L.F. Kooistra, E.A. Lange, and A.G. Pickett, Full-Size Pressure Vessel Testing and Its Application to Design, J. Eng. Power 86, 419-428 (1964).
54. P.S. Maiya and D.E. Busch, Effect of Surface Roughness on Low-Cycle Fatigue Behavior of Type 304 Stainless Steel, Met. Trans. 6A, 1761-1766 (1975).
55. P.S. Maiya, Effect of Surface Roughness and Strain Range on Low-Cycle Fatigue Behavior of Type 304 Stainless Steel, Scripta Metall. 9, 1277-1282 (1975).
56. C. Faidy, T. Le Courtois, E. de Fraguier, J.-A. Leduff, A. Lefrancois, and J. Dechelotte, Thermal Fatigue in French RHR System, Int. Conf. on Fatigue of Reactor Components, Napa, CA, July 31-August 2, 2000.
57. W.A. Van Der Sluys and S. Yukawa, Status of PVRC Evaluation of LWR Coolant Environmental Effects on the S-N Fatigue Properties of Pressure Boundary Materials, in Fatigue and Crack Growth: Environmental Effects, Modeling Studies, and Design Considerations, PVP Vol. 306, S. Yukawa, ed., American Society of Mechanical Engineers, New York, pp. 47-58 (1995).
58. W.E. Cooper, The Initial Scope and Intent of the Section III Fatigue Design Procedure, in Technical Information from Workshop on Cyclic Life and Environmental Effects in Nuclear Applications, Clearwater, Florida, January 20-21, 1992, Welding Research Council, Inc. New York, 1992.
59. M.A. Pompetzki, T.H. Topper, and D.L. DuQuesnay, The Effect of Compressive Underloads and Tensile Overloads on Fatigue Damage Accumulation in SAE 1045 Steel, Int. J. Fatigue 12 (3), 207-213 (1990).
60. A. Conle and T.H. Topper, Evaluation of Small Cycle Omission Criteria for Shortening of Fatigue Service Histories, Int. J. Fatigue 1, 23-28 (1979).
61. A. Conle and T.H. Topper, Overstrain Effects During Variable Amplitude Service History Testing, Int. J. Fatigue 2, 130-136 (1980).
62. Li Nian and Du Bai-Ping, Effect of Monotonic and Cyclic Prestrain on the Fatigue Threshold in Medium-Carbon steels, Int. J. Fatigue 14 (1), 41-44 (1992).
63. M.J. Manjoine, Fatigue Damage Models for Annealed Type 304 Stainless Steel under Complex Strain Histories, Trans. 6th Intl. Conf. on Structural Mechanics in Reactor Technology (SMiRT), Vol. L, 8/1, North-Holland Publishing Co., pp. 1-13 (1981).
64. Li Nian and Du Bai-Ping, The Effect of Low-Stress High-Cycle Fatigue on the Microstructure and Fatigue Threshold of a 40Cr Steel, Int. J. Fatigue 17 (1), 43-48 (1995).
65. E. Haibach and D. Schutz, Fatigue Life Evaluation with Particular Attention to Local Strain and Stress Time Histories, Proc. Inst. Mech. Eng. (1974).
66. D.J. Dowdell, H.H.E. Leipholz, and T.H. Topper, The Modified Life Law Applied to SAE-1045 Steel, Int. J. Fract. 31, 29-36 (1986).