Skip to main content
Top
Published in: Strength of Materials 4/2021

13-11-2021

Research of SCC Prediction Model for 304 Stainless Steel in the High-Temperature Water Environment

Authors: Y. H. Cui, J. L. Zhang

Published in: Strength of Materials | Issue 4/2021

Log in

Activate our intelligent search to find suitable subject content or patents.

search-config
loading …

Abstract

Stress corrosion cracking (SCC) is a failure mode determining the safety of dissimilar metal welded joints in nuclear power plants. It is also of great importance to establish an SCC crack propagation life prediction model for the safety of welded joints of practical engineering significance in nuclear power structural safety assessment. The creep constitutive mechanism of 304 stainless steel at 288°C was obtained in the autoclave creep experiment, and the finite element calculation method of SCC based on creep was set up. The creep field around the crack tip and the crack growth rate variation at different yield strength and stress intensity factor K were analyzed. The crack growth rate will increase with the latter characteristics. By comparing with the SCC experimental data, the prediction model accuracy was verified. The results provide a scientific basis for the prediction of the SCC rate of 304 stainless steel in the high-temperature water environment.

Dont have a licence yet? Then find out more about our products and how to get one now:

Springer Professional "Wirtschaft+Technik"

Online-Abonnement

Mit Springer Professional "Wirtschaft+Technik" erhalten Sie Zugriff auf:

  • über 102.000 Bücher
  • über 537 Zeitschriften

aus folgenden Fachgebieten:

  • Automobil + Motoren
  • Bauwesen + Immobilien
  • Business IT + Informatik
  • Elektrotechnik + Elektronik
  • Energie + Nachhaltigkeit
  • Finance + Banking
  • Management + Führung
  • Marketing + Vertrieb
  • Maschinenbau + Werkstoffe
  • Versicherung + Risiko

Jetzt Wissensvorsprung sichern!

Springer Professional "Technik"

Online-Abonnement

Mit Springer Professional "Technik" erhalten Sie Zugriff auf:

  • über 67.000 Bücher
  • über 390 Zeitschriften

aus folgenden Fachgebieten:

  • Automobil + Motoren
  • Bauwesen + Immobilien
  • Business IT + Informatik
  • Elektrotechnik + Elektronik
  • Energie + Nachhaltigkeit
  • Maschinenbau + Werkstoffe




 

Jetzt Wissensvorsprung sichern!

Literature
1.
go back to reference J. L. Zhang, Y. H. Cui, H. Xue, et al., “Research on crack growth behavior of nickel-based alloy 600 in safe-end welded joints,” Rare Metal Mat. Eng., 49, No. 5, 1496–1502 (2020). J. L. Zhang, Y. H. Cui, H. Xue, et al., “Research on crack growth behavior of nickel-based alloy 600 in safe-end welded joints,” Rare Metal Mat. Eng., 49, No. 5, 1496–1502 (2020).
2.
go back to reference C. Ma, Q. J. Peng, E. H. Han, et al., “Review of stress corrosion cracking of structural materials in nuclear power plants,” Journal of Chinese Society for Corrosion and Protection, 34, No. 1, 37–45 (2014). C. Ma, Q. J. Peng, E. H. Han, et al., “Review of stress corrosion cracking of structural materials in nuclear power plants,” Journal of Chinese Society for Corrosion and Protection, 34, No. 1, 37–45 (2014).
3.
go back to reference F. Q. Yang, H. Xue, L. Y. Zhao, and X. R. Fang, “A quantitative prediction model of SCC rate for nuclear structure materials in high-temperature water based on crack tip creep strain rate,” Nucl. Eng. Des., 278, No. 8, 686–692 (2014).CrossRef F. Q. Yang, H. Xue, L. Y. Zhao, and X. R. Fang, “A quantitative prediction model of SCC rate for nuclear structure materials in high-temperature water based on crack tip creep strain rate,” Nucl. Eng. Des., 278, No. 8, 686–692 (2014).CrossRef
4.
go back to reference F. P. Ford and P. L. Andresen, “Development and use of a predictive model of crack propagation in 304/316L, A533B/A508 and Inconel 600/182 alloys in 288°C water,” in: Proc. of the Third Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems (1988), pp. 789–800. F. P. Ford and P. L. Andresen, “Development and use of a predictive model of crack propagation in 304/316L, A533B/A508 and Inconel 600/182 alloys in 288°C water,” in: Proc. of the Third Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems (1988), pp. 789–800.
5.
go back to reference T. Shoji, Z. Lu, and H. Murakami, “Formulating stress corrosion cracking growth rates by combination of crack tip mechanics and crack tip oxidation kinetics,” Corros. Sci., 52, No. 3, 769–779 (2010).CrossRef T. Shoji, Z. Lu, and H. Murakami, “Formulating stress corrosion cracking growth rates by combination of crack tip mechanics and crack tip oxidation kinetics,” Corros. Sci., 52, No. 3, 769–779 (2010).CrossRef
6.
go back to reference M. M. Hall, Jr, “Critique of the Ford–Andresen film rupture model for aqueous stress corrosion cracking,” Corros. Sci., 51, No. 5, 1103–1106 (2009).CrossRef M. M. Hall, Jr, “Critique of the Ford–Andresen film rupture model for aqueous stress corrosion cracking,” Corros. Sci., 51, No. 5, 1103–1106 (2009).CrossRef
7.
go back to reference H. Xue and T. Shoji, “Quantitative prediction of EAC crack growth rate of sensitized type 304 stainless steel in boiling water reactor environments based on EPFEM,” J. Press. Vess.-T. ASME, 129, No. 3, 460–467 (2007).CrossRef H. Xue and T. Shoji, “Quantitative prediction of EAC crack growth rate of sensitized type 304 stainless steel in boiling water reactor environments based on EPFEM,” J. Press. Vess.-T. ASME, 129, No. 3, 460–467 (2007).CrossRef
8.
go back to reference M. M. Hall, Jr, “Film rupture model for aqueous stress corrosion cracking under constant and variable stress intensity factor,” Corros. Sci., 51, No. 2, 225–233 (2009).CrossRef M. M. Hall, Jr, “Film rupture model for aqueous stress corrosion cracking under constant and variable stress intensity factor,” Corros. Sci., 51, No. 2, 225–233 (2009).CrossRef
9.
go back to reference L. Zhang, K. Chen, D. Du, et al., “Characterizing the effect of creep on stress corrosion cracking of cold worked Alloy 690 in supercritical water environment,” J. Nucl. Mater., 492, 32–40 (2017).CrossRef L. Zhang, K. Chen, D. Du, et al., “Characterizing the effect of creep on stress corrosion cracking of cold worked Alloy 690 in supercritical water environment,” J. Nucl. Mater., 492, 32–40 (2017).CrossRef
10.
go back to reference K. Chen, D. Du, W. Gao, et al., “Effect of cold work on the stress corrosion cracking behavior of Alloy 690 in supercritical water environment,” J. Nucl. Mater., 498, 117–128 (2018).CrossRef K. Chen, D. Du, W. Gao, et al., “Effect of cold work on the stress corrosion cracking behavior of Alloy 690 in supercritical water environment,” J. Nucl. Mater., 498, 117–128 (2018).CrossRef
11.
go back to reference S. Maharjan, X. C. Zhang, F. Z. Xuan, et al., “Residual stresses within oxide layers due to lateral growth strain and creep strain: Analytical modeling,” J. Appl. Phys., 110, No. 6, 063511 (2011).CrossRef S. Maharjan, X. C. Zhang, F. Z. Xuan, et al., “Residual stresses within oxide layers due to lateral growth strain and creep strain: Analytical modeling,” J. Appl. Phys., 110, No. 6, 063511 (2011).CrossRef
12.
go back to reference D. Du, K. Chen, L. Yu, et al., “SCC crack growth rate of cold worked 316L stainless steel in PWR environment,” J. Nucl. Mater., 456, 228–234 (2015).CrossRef D. Du, K. Chen, L. Yu, et al., “SCC crack growth rate of cold worked 316L stainless steel in PWR environment,” J. Nucl. Mater., 456, 228–234 (2015).CrossRef
13.
go back to reference H. Xue, Y. Sato, and T. Shoji, “Quantitative estimation of the growth of environmentally assisted cracks at flaws in light water reactor components,” J. Press. Vess.-T. ASME, 131, No. 1, 011404 (2009).CrossRef H. Xue, Y. Sato, and T. Shoji, “Quantitative estimation of the growth of environmentally assisted cracks at flaws in light water reactor components,” J. Press. Vess.-T. ASME, 131, No. 1, 011404 (2009).CrossRef
14.
go back to reference Y. Yi and G. S. Was, “Stress and temperature dependence of creep in Alloy 600 in primary water,” Metall. Mater. Trans. A, 32, No. 10, 2553–2560 (2001).CrossRef Y. Yi and G. S. Was, “Stress and temperature dependence of creep in Alloy 600 in primary water,” Metall. Mater. Trans. A, 32, No. 10, 2553–2560 (2001).CrossRef
15.
go back to reference Y. Xue, Research on Structure and Properties of Duplex Stainless Steel for Nuclear Power Plant Pipes, Xi’an Technological University (2010). Y. Xue, Research on Structure and Properties of Duplex Stainless Steel for Nuclear Power Plant Pipes, Xi’an Technological University (2010).
16.
go back to reference L. Dong, Q. Peng, E. H. Han, et al., “Microstructure and intergranular stress corrosion cracking susceptibility of a SA508-52M-316L dissimilar metal weld joint in primary water,” J. Mater. Sci. Technol., 34, No. 8, 1281–1292 (2018).CrossRef L. Dong, Q. Peng, E. H. Han, et al., “Microstructure and intergranular stress corrosion cracking susceptibility of a SA508-52M-316L dissimilar metal weld joint in primary water,” J. Mater. Sci. Technol., 34, No. 8, 1281–1292 (2018).CrossRef
17.
go back to reference ASTM D5045-99(2007)e1, Standard Test Methods for Plane-Strain Fracture Toughness and Strain Energy Release Rate of Plastic Materials, ASTM International, West Conshohocken, PA (2007). ASTM D5045-99(2007)e1, Standard Test Methods for Plane-Strain Fracture Toughness and Strain Energy Release Rate of Plastic Materials, ASTM International, West Conshohocken, PA (2007).
18.
go back to reference W. Ramberg and W. R. Osgood, Description of Stress–Strain Curves by Three Parameters, Technical Note No. 902 (1943). W. Ramberg and W. R. Osgood, Description of Stress–Strain Curves by Three Parameters, Technical Note No. 902 (1943).
19.
go back to reference J. S. Ma, Finite Element Analysis of 3D Mixed-Mode Fracture Stress Intensity Factors [in Chinese], Harbin Engineering University (2008). J. S. Ma, Finite Element Analysis of 3D Mixed-Mode Fracture Stress Intensity Factors [in Chinese], Harbin Engineering University (2008).
20.
go back to reference Y. H. Cui, J. L. Zhang, and X. L. Li, “Influence of yield stress on the SCC creep mechanical field and growth rate at the tip of 304 stainless steel,” Foundry Technol., 41, No. 12, 1117–1121 (2020). Y. H. Cui, J. L. Zhang, and X. L. Li, “Influence of yield stress on the SCC creep mechanical field and growth rate at the tip of 304 stainless steel,” Foundry Technol., 41, No. 12, 1117–1121 (2020).
21.
go back to reference K. Arioka, T. Yamada, T. Terachi, et al., “Cold work and temperature dependence of stress corrosion crack growth of austenitic stainless steels in hydrogenated and oxygenated high temperature water,” Corrosion, 63, No. 12, 1114–1123 (2007).CrossRef K. Arioka, T. Yamada, T. Terachi, et al., “Cold work and temperature dependence of stress corrosion crack growth of austenitic stainless steels in hydrogenated and oxygenated high temperature water,” Corrosion, 63, No. 12, 1114–1123 (2007).CrossRef
22.
go back to reference O. K. Chopra and A. S. Rao, “A review of irradiation effects on LWR core internal materials IASCC susceptibility and crack growth rates of austenitic stainless steels,” J. Nucl. Mater., 409, No. 3, 235–256 (2011).CrossRef O. K. Chopra and A. S. Rao, “A review of irradiation effects on LWR core internal materials IASCC susceptibility and crack growth rates of austenitic stainless steels,” J. Nucl. Mater., 409, No. 3, 235–256 (2011).CrossRef
Metadata
Title
Research of SCC Prediction Model for 304 Stainless Steel in the High-Temperature Water Environment
Authors
Y. H. Cui
J. L. Zhang
Publication date
13-11-2021
Publisher
Springer US
Published in
Strength of Materials / Issue 4/2021
Print ISSN: 0039-2316
Electronic ISSN: 1573-9325
DOI
https://doi.org/10.1007/s11223-021-00319-6

Other articles of this Issue 4/2021

Strength of Materials 4/2021 Go to the issue

Premium Partners