Effect of Light Water Reactor Water Environments on the Fatigue Life of Reactor Materials

Chopra, O. K.; Stevens, G. L.; Tregoning, R.; Rao, A. S.

doi:10.1115/1.4035885

Title: Effect of Light Water Reactor Water Environments on the Fatigue Life of Reactor Materials

Journal Article · Fri Oct 06 00:00:00 EDT 2017 · Journal of Pressure Vessel Technology

DOI:https://doi.org/10.1115/1.4035885· OSTI ID:1400395

Chopra, O. K. ^[1]; Stevens, G. L. ^[2]; Tregoning, R. ^[3]; Rao, A. S. ^[3]

Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Science Division
Structural Integrity Associates, Inc., Huntersville, NC (United States)
US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Division of Engineering

The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) provides rules for the design of Class 1 components of nuclear power plants. Figures I-9.1 through I-9.6 of Appendix I to Section III of the Code specify fatigue design curves for applicable structural materials. However, the Code design curves do not explicitly address the effects of light water reactor (LWR) water environments. Existing fatigue strain-vs.-life (ε-N) laboratory data illustrate potentially significant effects of LWR water environments on the fatigue resistance of pressure vessel and piping steels. Extensive studies have been conducted at Argonne National Laboratory and elsewhere since 1990 to investigate the effects of LWR environments on the fatigue life of piping and pressure vessel steels. This article summarizes the results of these studies. Existing fatigue ε-N data were evaluated to identify the various material, environmental, and loading conditions that influence fatigue crack initiation; a methodology for estimating fatigue lives as a function of these parameters was developed. The effects were incorporated into the ASME Code Section III fatigue evaluations in terms of an environmental correction factor, F_en, which is defined as the ratio of fatigue life in air at room temperature to the fatigue life in the LWR water environment at reactor operating temperatures. Available fatigue data were used to develop fatigue design curves for carbon and low-alloy steels, austenitic stainless steels, and nickel-chromium-iron (NiCr-Fe) alloys and their weld metals in air at room temperature. A review of the Code Section III fatigue adjustment factors of 2 on strain and 20 on life is also presented and the possible conservatism inherent in the choice of these adjustment factors is evaluated. A brief description of potential effects of neutron irradiation on fatigue crack initiation for these structural materials is also presented.

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Research Organization:: Argonne National Lab. (ANL), Argonne, IL (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES); USNRC

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 1400395

Journal Information:: Journal of Pressure Vessel Technology, Vol. 139, Issue 6; ISSN 0094-9930

Publisher:: ASMECopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 4 works

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References (48)

The effect of low-stress high-cycle fatigue on themicrostructure and fatigue threshold of a 40Cr steel Nian, L. International Journal of Fatigue, Vol. 17, Issue 1 https://doi.org/10.1016/0142-1123(95)93049-8	journal	January 1995
A review of fatigue failures in LWR plants in Japan Iida, Kunihiro Nuclear Engineering and Design, Vol. 138, Issue 3 https://doi.org/10.1016/0029-5493(92)90068-7	journal	December 1992
Effect of surface roughness on low-cycle fatigue behavior of type 304 stainless steel Maiya, P. S.; Busch, D. E. Metallurgical Transactions A, Vol. 6, Issue 9 https://doi.org/10.1007/bf02642305	journal	September 1975
Influence of cyclic strain rate on environmentally assisted cracking behavior of pressure vessel steel in high-temperature water Wu, X. Q.; Katada, Y. Materials Science and Engineering: A, Vol. 379, Issue 1-2 https://doi.org/10.1016/j.msea.2004.02.051	journal	August 2004
The Modified Rate Approach Method to Evaluate Fatigue Life Under Synchronously Changing Temperature and Strain Rate in Elevated Temperature Water Tsutsumi, Kazuya; Higuchi, Makoto; Iida, Kunihiro ASME 2002 Pressure Vessels and Piping Conference, Pressure Vessel and Piping Codes and Standards https://doi.org/10.1115/pvp2002-1227	conference	August 2008
Discussion on Fatigue Design Curves for Stainless Steels Solin, Jussi; Reese, Sven; Mayinger, Wolfgang ASME 2011 Pressure Vessels and Piping Conference, Volume 1: Codes and Standards https://doi.org/10.1115/pvp2011-57943	conference	May 2012
Effect of Loading Signal Shape and of Surface Finish on the Low Cycle Fatigue Behavior of 304L Stainless Steel in PWR Environment Le Duff, Jean Alain; Lefranc¸ois, Andre´; Vernot, Jean Philippe ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference, ASME 2010 Pressure Vessels and Piping Conference: Volume 1 https://doi.org/10.1115/pvp2010-26027	conference	January 2011
Strain-amplitude dependent fatigue resistance of low-alloy pressure vessel steels in high-temperature water Wu, X. Q.; Katada, Y. Journal of Materials Science, Vol. 40, Issue 8 https://doi.org/10.1007/s10853-005-1216-4	journal	April 2005
Effects of surface roughness and strain range on the low-cycle fatigue behavior of type 304 stainless steel Maiya, P. S. Scripta Metallurgica, Vol. 9, Issue 11 https://doi.org/10.1016/0036-9748(75)90424-x	journal	November 1975
Influence of surface finish on fatigue cracking behavior of reactor pressure vessel steel in high temperature water Wu, X. Q.; Guan, H.; Han, E. H. Materials and Corrosion, Vol. 57, Issue 11 https://doi.org/10.1002/maco.200503963	journal	November 2006
Effect of monotonic and cyclic prestrain on the fatigue threshold in medium-carbon steels Nian, Li; Bai-Ping, Du International Journal of Fatigue, Vol. 14, Issue 1 https://doi.org/10.1016/0142-1123(92)90152-3	journal	January 1992
Effects of Water Flow Rate on Fatigue Life of Carbon and Stainless Steels in Simulated LWR Environment Hirano, Akihiko; Yamamoto, Michiyoshi; Sakaguchi, Katsumi ASME/JSME 2004 Pressure Vessels and Piping Conference, Pressure Vessel and Piping Codes and Standards https://doi.org/10.1115/pvp2004-2680	conference	August 2008
Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments Chopra, O. K.; Shack, W. J. Journal of Pressure Vessel Technology, Vol. 121, Issue 1 https://doi.org/10.1115/1.2883667	journal	February 1999
Final Proposal of Environmental Fatigue Life Correction Factor (Fen) for Structural Materials in LWR Water Environment Higuchi, Makoto; Sakaguchi, Katsumi; Nomura, Yuichiro ASME 2007 Pressure Vessels and Piping Conference, Volume 1: Codes and Standards https://doi.org/10.1115/pvp2007-26100	conference	August 2009
Overstrain effects during variable amplitude service history testing Conle, A.; Topper, T. International Journal of Fatigue, Vol. 2, Issue 3 https://doi.org/10.1016/0142-1123(80)90015-8	journal	July 1980
Effects of Water Flow Rate on Fatigue Life of Ferritic and Austenitic Steels in Simulated LWR Environment Hirano, Akihiko; Yamamoto, Michiyoshi; Sakaguchi, Katsumi ASME 2002 Pressure Vessels and Piping Conference, Pressure Vessel and Piping Codes and Standards https://doi.org/10.1115/pvp2002-1231	conference	August 2008
Effects of Surface Finish and Loading Conditions on the Low Cycle Fatigue Behavior of Austenitic Stainless Steel in PWR Environment for Various Strain Amplitude Levels Le Duff, Jean Alain; Lefranc¸ois, Andre´; Vernot, Jean Philippe ASME 2009 Pressure Vessels and Piping Conference, Volume 3: Design and Analysis https://doi.org/10.1115/pvp2009-78129	conference	July 2010
Temperature Dependence of Reactor Water Environmental Fatigue Effects on Carbon, Low Alloy and Austenitic Stainless Steels O’Donnell, William James; O’Donnell, William John ASME 2008 Pressure Vessels and Piping Conference, Volume 1: Codes and Standards https://doi.org/10.1115/pvp2008-61917	conference	July 2009
Strain Fatigue and Tensile Behavior of Inconel® 718 from Room Temperature to 650°C Etris, Sf; Fiorini, Yr; Lieb, Kc Journal of Testing and Evaluation, Vol. 2, Issue 4 https://doi.org/10.1520/jte10109j	journal	January 1974
Formation and growth of cracking in feed water pipes and RPV nozzles Kussmaul, K.; Blind, D.; Jansky, J. Nuclear Engineering and Design, Vol. 81, Issue 1 https://doi.org/10.1016/0029-5493(84)90256-5	journal	August 1984
The Growth of Microstructurally Small Fatigue Cracks in a Ferritic-Pearlitic Steel Tokaji, Keiro; Ogawa, Takeshi; Osako, Shuji Fatigue & Fracture of Engineering Materials and Structures, Vol. 11, Issue 5 https://doi.org/10.1111/j.1460-2695.1988.tb01387.x	journal	September 1988
Strain-induced corrosion cracking of low-alloy steels in LWR systems — case histories and identification of conditions leading to susceptibility Hickling, J.; Blind, D. Nuclear Engineering and Design, Vol. 91, Issue 3 https://doi.org/10.1016/0029-5493(86)90084-1	journal	February 1986
Corrosion Fatigue Behavior of Low-Alloy Pressure Vessel Steels in High Temperature Water Under Multi-Factor Conditions Wu, Xinqiang; Katada, Yasuyuki Journal of Pressure Vessel Technology, Vol. 126, Issue 4 https://doi.org/10.1115/1.1811107	journal	November 2004
An analysis of the effects of sulphur content and potential on corrosion fatigue crack growth in reactor pressure vessel steels Atkinson, J. D.; Yu, J.; Chen, Z. -Y. Corrosion Science, Vol. 38, Issue 5 https://doi.org/10.1016/0010-938x(95)00164-f	journal	May 1996
Short Crack Fatigue Behaviour in a Medium Carbon Steel Rios, E. R. de los; Tang, Z.; Miller, K. J. Fatigue & Fracture of Engineering Materials and Structures, Vol. 7, Issue 2 https://doi.org/10.1111/j.1460-2695.1984.tb00408.x	journal	February 1984
Design of Pressure Vessels for Low-Cycle Fatigue Langer, B. F. Journal of Basic Engineering, Vol. 84, Issue 3 https://doi.org/10.1115/1.3657332	journal	September 1962
Fatigue of Stabilized SS and 316 NG Alloy in PWR Environment Solin, Jussi P. ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference, Volume 1: Codes and Standards https://doi.org/10.1115/pvp2006-icpvt-11-93833	conference	July 2008
Influence of Mean Stress on the Fatigue Behavior of 304L SS in Air and PWR Water Solomon, H. D.; Amzallag, C.; Vallee, A. J. ASME 2005 Pressure Vessels and Piping Conference, Volume 1: Codes and Standards https://doi.org/10.1115/pvp2005-71064	conference	July 2008
Environmental Fatigue Testing of Type 304L Stainless Steel U-Bends in Simulated PWR Primary Water Hickling, John; Kilian, Renate; Spain, Leslie ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference, Volume 1: Codes and Standards https://doi.org/10.1115/pvp2006-icpvt-11-93318	conference	July 2008
Influence of strain rate change on corrosion fatigue behavior of A533B steel in simulated BWR water Wu, X. Q.; Katada, Y. Journal of Materials Science, Vol. 39, Issue 7 https://doi.org/10.1023/b:jmsc.0000020018.37230.df	journal	April 2004
Thermal fatigue strength of type 304 stainless steel in simulated BWR environment Hayashi, Makoto Nuclear Engineering and Design, Vol. 184, Issue 1 https://doi.org/10.1016/s0029-5493(97)00372-5	journal	August 1998
Fatigue-Crack Propagation in Fast-Neutron-Irradiated Types-304 and -316 Stainless Steels James, L. A.; Knecht, R. L. Nuclear Technology, Vol. 19, Issue 3 https://doi.org/10.13182/nt73-a15876	journal	September 1973
Strain-rate dependence of low cycle fatigue behavior in a simulated BWR environment Wu, Xinqiang; Katada, Yasuyuki Corrosion Science, Vol. 47, Issue 6 https://doi.org/10.1016/j.corsci.2004.07.037	journal	June 2005
Full-Size Pressure Vessel Testing and Its Application to Design Kooistra, L. F.; Lange, E. A.; Pickett, A. G. Journal of Engineering for Power, Vol. 86, Issue 4 https://doi.org/10.1115/1.3677630	journal	October 1964
The effect of fast neutron irradiation upon the fatigue-crack propagation behavior of two austenitic stainless steels James, Lee A. Journal of Nuclear Materials, Vol. 59, Issue 2 https://doi.org/10.1016/0022-3115(76)90133-1	journal	February 1976
Fatigue crack propagation in neutron irradiated type 304 and type 308 stainless steel plate and weld materials Michel, D. J.; Smith, H. H. Journal of Nuclear Materials, Vol. 71, Issue 1 https://doi.org/10.1016/0022-3115(77)90202-1	journal	December 1977
Fatigue strength correction factors for carbon and low-alloy steels in oxygen-containing high-temperature water Higuchi, Makoto; Iida, Kunihiro Nuclear Engineering and Design, Vol. 129, Issue 3 https://doi.org/10.1016/0029-5493(91)90138-8	journal	August 1991
Effects of LWR Coolant Environments on Fatigue Lives of Austenitic Stainless Steels Chopra, O. K.; Gavenda, D. J. Journal of Pressure Vessel Technology, Vol. 120, Issue 2 https://doi.org/10.1115/1.2842228	journal	May 1998
Environmental factor approach to account for water effects in pressure vessel and piping fatigue evaluations Mehta, H. S.; Gosselin, S. R. Nuclear Engineering and Design, Vol. 181, Issue 1-3 https://doi.org/10.1016/s0029-5493(97)00344-0	journal	May 1998
Effects of Surface Finish and Loading Conditions on the Low Cycle Fatigue Behavior of Austenitic Stainless Steel in PWR Environment: Comparison of LCF Test Results With NUREG/CR-6909 Life Estimations Le Duff, Jean Alain; Lefranc¸ois, Andre´; Vernot, Jean Philippe ASME 2008 Pressure Vessels and Piping Conference, Volume 3: Design and Analysis https://doi.org/10.1115/pvp2008-61894	conference	July 2009
Effects of Continuous Strain Rate Changing on Environmental Fatigue for Stainless Steels in PWR Environment Nomura, Yuichiro; Asada, Seiji; Nakamura, Takao ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference, ASME 2010 Pressure Vessels and Piping Conference: Volume 1 https://doi.org/10.1115/pvp2010-25194	conference	January 2011
Low Cycle Fatigue of Commercial Piping Steels in a BWR Primary Water Environment Hale, D. A.; Wilson, S. A.; Kass, J. W. Journal of Engineering Materials and Technology, Vol. 103, Issue 1 https://doi.org/10.1115/1.3224967	journal	January 1981
The effect of compressive underloads and tensile overloads on fatigue damage accumulation in SAE 1045 steel Pompetzki, M.; Topper, T.; Duquesnay, D. International Journal of Fatigue, Vol. 12, Issue 3 https://doi.org/10.1016/0142-1123(90)90097-x	journal	May 1990
Dynamic strain aging in the high-temperature low-cycle fatigue of SA508 Cl. 3 forging steel Lee, Byung Ho; Kim, In Sup Journal of Nuclear Materials, Vol. 226, Issue 1-2 https://doi.org/10.1016/0022-3115(95)00092-5	journal	October 1995
Effects of loading factors on environmental fatigue behavior of low-alloy pressure vessel steels in simulated BWR water Wu, Xinqiang; Han, Enhou; Ke, Wei Nuclear Engineering and Design, Vol. 237, Issue 12-13 https://doi.org/10.1016/j.nucengdes.2006.09.043	journal	July 2007
Fatigue Design Criteria for Pressure Vessel Alloys Jaske, C. E.; O’Donnell, W. J. Journal of Pressure Vessel Technology, Vol. 99, Issue 4 https://doi.org/10.1115/1.3454577	journal	November 1977
On the mechanisms of environment sensitive cyclic crack growth of nuclear reactor pressure vessel steels Hänninen, H.; Törrönen, K.; Kemppainen, M. Corrosion Science, Vol. 23, Issue 6 https://doi.org/10.1016/0010-938x(83)90126-9	journal	January 1983
Corrosion Fatigue Behavior of Low-Alloy Pressure Vessel Steels in High Temperature Water Under Multi-Factor Conditions Wu, Xinqiang; Katada, Yasuyuki ASME/JSME 2004 Pressure Vessels and Piping Conference, Pressure Vessel and Piping Codes and Standards https://doi.org/10.1115/pvp2004-2676	conference	August 2008

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