Skip to main content
SpringerLink
Log in

Role of Cavity Formation on Crack Growth of Cold-Worked Carbon Steel, TT 690 and MA 600 in High Temperature Water

  • Conference paper
Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors

Abstract

The role of cavity formation on crack growth of intergranular stress corrosion cracking (IGSCC) in high temperature water and creep cracking was examined in quantitatively for cold worked carbon steel (ASTM A106 (UNS K03006, CW carbon steel), Alloy 690 (UNSN06690, CW TT 690), and Alloy 600 (UNSN06600, CW MA 600). Three important patterns were observed: First, cavities were observed at grain boundaries just ahead crack tips and crack wall after tests in gas and high temperature water for all test materials. Second, population of cavities decreased with distance from crack tips and crack wall. This result seems to suggest that cavities will form at high stress region such as crack tips before crack advance as crack embryos. Third, good correlation was observed between the rate of cavity formation and crack growth of IGSCC and intergranular creep cracking not only carbon steel, but also TT690 and MA600. Finally, the formation of crack embryos from the collapse of vacancies induced by cold work and absorbed hydrogen play an important role on the process of crack growth both of SCC and creep for CW carbon steel, CW TT690, and CW MA600 in high temperature water.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Log in via an institution
Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 319.00
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. H. Choi, F.H. Beck, Z. Szklarska-Smialowska, and D.D. Macdonald, “Stress Corrosion Cracking of ASTM A508 Cl2 Steel in Oxygenated Water at Elevated Temperatures,” Corrosion, 38(1982), p.136.

    Article  Google Scholar 

  2. J. Kuniya, I. Masaoka, R. Sasaki, H. Itoh, and T. Okazaki, “Stress Corrosion Cracking Susceptibility of Low Alloy Steels Used for Reactor Pressure Vessel in High Temperature Oxygenated Water,” Transactions of the ASME, 107(1985), p.430.

    Google Scholar 

  3. M.O. Speidel, “Stress Corrosion Cracking of Steam Turbine Steels- An Overview”, Proceedings of the 2nd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactor, D. Cubicciotti chair, American Nuclear Society, Monterey, CA, (1985), p.267.

    Google Scholar 

  4. J. Hickling, “Strain Induced Corrosion Cracking of Low Alloy Steels in LWR Systems-Case History and Identification of Conditions Leading to Susceptibility,” Nuclear Engineering and Design, 91(1986), p.305.

    Article  Google Scholar 

  5. M.O. Speidel, “Stress Corrosion Cracking and Corrosion Fatigue of Nuclear Reactor Pressure Vessel Steels in Hot Water,” J. Materials Engineering, 9(1987), p.157.

    Article  Google Scholar 

  6. M.O. Speidel and R.M. Magdowski, “Stress Corrosion Cracking of Nuclear Reactor Pressure Vessel and Piping Steels,” International Journal of Pressure Vessels and Piping, 34(1988), p.119.

    Article  Google Scholar 

  7. P.M. Scott and D.R. Tice, “Stress Corrosion Cracking in Low Alloy Steels,” Nuclear Engineering and Design, 119(1990), p.399.

    Article  Google Scholar 

  8. J. Heldt and H.P. Seifert, “Stress Corrosion Cracking of Reactor Pressure Vessel Steels Under Boiling Water Reactor Condition,” Proceedings of the 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, S. Bruemmer, P. Ford, and G.S. Was editors, TMS, Newport Beach, CA, (1999), p.901.

    Google Scholar 

  9. J. Hickling, “Strain-induced corrosion cracking of low alloy steels under BWR conditions: are there still open issues?” Proceedings of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactor, P. Ford, G.S. Was Chairs, NACE, Lake Tahoe, CA, (2001).

    Google Scholar 

  10. H. Hanninen, Y.Y. Yagodzinskyy, O. Tarasenko, H.P. Seifert, U. Ehrnsten, and P. Aaltonen, “Effect of Dynamic Strain Aging on Environment-Assisted Cracking of Low Alloy Pressure Vessel and Piping Steels,” Proceedings of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactor, P. Ford, G.S. Was Chairs, NACE, Lake Tahoe, CA, (2001).

    Google Scholar 

  11. S. Ritter and H.P. Seifert, “Stress Corrosion Cracking Behavior of Low Alloy Reactor Pressure Vessel Steels and of a Weld Material under Simulated BWR Environment,” Corrosion 2003, Paper No.03664, NACE (2003).

    Google Scholar 

  12. H.P. Seifert, S. Ritter, and J. Hickling, “Environmentally-Assisted Cracking of Low-Alloy RPV and Piping Steels under LWR Conditions,” Proceedings of the 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, G. S. Was chair, American Nuclear Society, Stevenson, WA, (2003).

    Google Scholar 

  13. A. Roth, B. Devrient, D. Gomez-Briceno, J. Lapena, M. Ernestova, M. Zamboch, U. Ehrnsten, J. Fohl, T. Weissenberg, H.P. Seifert, and S. Ritter, “The Effect of Transition on The Crack Growth Behavior of Low Alloy Steels for Pressure Boundary Components under Light Water Reactor Operating Conditions,” Proceedings of 12th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, L. Nelson, P. King and T. Allen, editors, TMS, Salt Lake, UT (2005).

    Google Scholar 

  14. H.P. Seifert and S. Ritter, “Mitigation Effect of Hydrogen Water Chemistry on Stress Corrosion and Low Frequency Corrosion Fatigue Crack Growth in Low Alloy Steels,” Proceedings of 12th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, L. Nelson, P. King and T. Allen, editors, TMS, Salt Lake, UT (2005).

    Google Scholar 

  15. H.P. Seifert and S. Ritter, “Effect of Corrosion Potential on Corrosion Fatigue Crack Growth of Low Alloy Steels in High Temperature Water,” Proceedings of the 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, P. King and T. Allen chairs, Canadian Nuclear Society, Stevenson, Whistler, B.C., Canada, (2007).

    Google Scholar 

  16. A. Roth and J. Hickling, “Crack Initiation Due to Environmentally Assisted Cracking in Carbon and Low Alloy Steels Exposed to High Temperature Water,” Proceedings of the 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, P. King and T. Allen chairs, Canadian Nuclear Society, Stevenson, Whistler, B.C., Canada, (2007).

    Google Scholar 

  17. H.P. Seifert and S. Ritter, “Stress corrosion cracking of low alloy reactor pressure vessel steels under boiling water reactor conditions,” Journal of Nuclear Materials, 372(2008), p.114.

    Article  Google Scholar 

  18. H.P. Seifert and S. Ritter, “Strain induced corrosion cracking behavior of low alloy steels under boiling reactor conditions,” Journal of Nuclear Materials, 378(2008), p.312.

    Article  Google Scholar 

  19. M. Wright, P. Poruks, and S. Liu, “Role of Cold Work in CANDU Feeder Cracking,” Proceedings-2007 AECL/COG/EPRI Workshop on Cold Work in Iron- and Nickel-Based Alloys Exposed to High Temperature Water Environments, Toronto, Canada, (2007).

    Google Scholar 

  20. M. Wright, “Crack Initiation and Early Stages of Crack Growth in CANDU Feeder Pipes,” The SCC Initiation Workshop, Beaune, France, (2008).

    Google Scholar 

  21. J.P. Slade and T.S. Gendron, “Flow Accelerated Corrosion and Cracking of Carbon Steel Piping in Primary Water-Operating Experience at the Point Lepreau Generating Station,” Proceedings of 12th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, L. Nelson, P. King and T. Allen editors, TMS, Salt Lake, UT, (2005).

    Google Scholar 

  22. K. Arioka, T. Miyamoto, T. Yamada, and T. Terachi, Corrosion, 66 (2010): p.015008.

    Article  Google Scholar 

  23. P.L. Andresen, M.M. Morra, J. Hickling, Al Ahluwalia, and J. Wilson, “PWSCC of Alloys 690, 52 and 152,” Proceedings of the 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, P. King and T. Allen chairs, Canadian Nuclear Society, Stevenson, Whistler, B.C., Canada, (2007)

    Google Scholar 

  24. P.L. Andresen and M.M. Morra, “Effect of cold work on SCC growth rate and fracture properties of stainless steel and Ni alloys,” Proceedings-2007 AECL/COG/EPRI Workshop on Cold Work in Iron- and Nickel-Based Alloys Exposed to High Temperature Water Environments, Toronto, Canada, (2007)

    Google Scholar 

  25. D.J. Paraventi and W.C. Moshier, “Alloy 690 SCC growth rate testing,” Proceedings-2007 AECL/COG/EPRI Workshop on Cold Work in Iron- and Nickel-Based Alloys Exposed to High Temperature Water Environments, Toronto, Canada, (2007)

    Google Scholar 

  26. M. B. Toloczko and S. M. Bruemmer, “Crack-Growth Response of Alloy 690 in Simulated PWR Primary Water,” Proc. 14th International Conference Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, T. Allen chair, American Nuclear Society, Virginia Beach, VA, (2009)

    Google Scholar 

  27. B. Alexandreanu, Y. Yang, Y. Chen, and W.J. Shack, “The Stress Corrosion Cracking Behavior of Alloy 690 and 152 Weld in the PWR Environment,” Proc. 14th International Conference Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, American Nuclear Society, T. Allen chair, American Nuclear Society, Virginia Beach, VA, (2009)

    Google Scholar 

  28. K. Arioka, T. Miyamoto, T. Yamada, and T. Terachi, Corrosion, 67 (2011): p.035006.

    Article  Google Scholar 

  29. J. Takamura, Zairyou-Kyoudo no Kiso 4th edition, Kyoto University Gakujyutu Shuppannkai,(2004).

    Google Scholar 

  30. Y. Yamazaki, Y. Iijima, and M. Okada, Acta Materialia, 52, (2004), p.1247.

    Article  Google Scholar 

  31. T. Iida, Y. Yamazaki, T. Kobayashi, Y. Iijima, and Y. Fukai, Acta Materialia, 53(2005), p.3083.

    Article  Google Scholar 

  32. Y. Fukai and N. Okuma, Journal of Applied Physics, 32(1993), p.1256.

    Article  Google Scholar 

  33. Y. Fukui, M. Yamakata, and T. Yagi, Z.Phys.Chem., 179(1993), p.119.

    Article  Google Scholar 

  34. Y. Fukai and N. Okuma, Physical Review Letter, 73(1994), p.1640.

    Article  Google Scholar 

  35. H.K. Birnbaum, C. Buckley, F. Zeides, E. Sirois, P. Rozenak, S. Spooner, and J.S. Lin, Journal of Alloys and Compounds, 253–254(1997), p.260.

    Article  Google Scholar 

  36. Y. Iijima, K. Kimura, K. Hirano, Acta Metall., 36(1988); p.2811.

    Article  Google Scholar 

  37. C.G. Lee, Y. Iijima, T. Hiratani, K. Hirano, Mater.Trans., JIM, 31(1990): p.255.

    Article  Google Scholar 

  38. Y. Iijima, K. Kimura, C.G. Lee, K. Hirano, Mater.Trans., JIM, 34(1993): p.20.

    Article  Google Scholar 

  39. H. Nitta, T. Yamamoto, R. Kanno, K. Takasawa, T. Iida, Y. Yamasaki, S. Ogu, Y. Iijima, Acta Mater., 50(2002): p.4117.

    Article  Google Scholar 

  40. Y. Iijima, J.Phase Equilibria and Diffusion, 26(2005): p.466.

    Article  Google Scholar 

  41. N.R. Quick, H.H. Johnson, Acta Met., 26(1978): p.903.

    Article  Google Scholar 

  42. H. Hagi, Mater.Trans., JIM, 35(1994): p.112.

    Article  Google Scholar 

  43. B. Pieraggi, R.A. Rapp, Acta metall., 36 (1988); p. 1281.

    Article  Google Scholar 

  44. B. Pieraggi, R.A. Rapp, J. Electrochem. Soc., 140 (1993); p. 2844.

    Article  Google Scholar 

  45. B. Pieraggi, R.A. Rapp, Mat. High Temp. 12, (1994); p. 229.

    Article  Google Scholar 

  46. B. Pieraggi, B. MacDougall, R.A. Rapp, Corrosion Science, 47 (2005); p. 247.

    Article  Google Scholar 

Download references

Author information

Authors and Affiliations

  1. Institute of Nuclear Safety System, Incorporated, 64 Sata, Mihama-cho, Mikata-gun, Fukui, 919-1205, Japan

    Koji Arioka, Takuyo Yamada & Takumi Terachi

  2. Kobe Material Testing Laboratory Co., Ltd., 47-13 Niijima, Harima-cho, Kako-gun, Hyogo, 675-0155, Japan

    Tomoki Miyamoto

Authors
  1. Koji Arioka
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Tomoki Miyamoto
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Takuyo Yamada
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. Takumi Terachi
    View author publications

    You can also search for this author in PubMed Google Scholar

Editor information

Editors and Affiliations

  1. Oak Ridge National Laboratory, USA

    Jeremy T. Busby

  2. Electric Power Research Institute, USA

    Gabriel Ilevbare

  3. GE Global Research Center, USA

    Peter L. Andresen

Rights and permissions

Reprints and permissions

Copyright information

© 2011 TMS (The Minerals, Metals & Materials Society)

About this paper

Cite this paper

Arioka, K., Miyamoto, T., Yamada, T., Terachi, T. (2011). Role of Cavity Formation on Crack Growth of Cold-Worked Carbon Steel, TT 690 and MA 600 in High Temperature Water. In: Busby, J.T., Ilevbare, G., Andresen, P.L. (eds) Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer, Cham. https://doi.org/10.1007/978-3-319-48760-1_5

Download citation

Publish with us

Policies and ethics

Search

Navigation