Skip to main content

Abstract

Tapered uniaxial tensile samples under constant load and bent ring samples under constant strain were used to investigate the stress corrosion cracking (SCC) of Alloy 600 and 690 in supercritical water. To verify the effectiveness of the tapered tensile sample design, the SCC of two 304 stainless steels with high and low carbon content were tested in supercritical water at 400°C, 25MPa and 10–15ppb dissolved oxygen. Both testing methods are effective to initiate SCC in 304SS, Alloy 600 and 690. Based on the bent ring SCC testing, the SCC resistance of Alloy 690 in supercritical water is lower than Alloy 600. This unexpected lower SCC resistance is probably due to the much lower tensile ductility (less than 10%) of the tested Alloy 690 as compared with the standard 40–50% ductility and the severe plastic deformation and strain in the bent ring samples. The large TiN particles and their inhomogeneous distribution in the alloy may promote the SCC initiation in this specific Alloy 690 in the bent ring samples. SCC is more likely to initiate from the Electrical Discharge Machined (EDM) or end mill machined surfaces than from ground and polished surfaces.

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

Access this chapter

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. Jeff Gorman, Steve Hunt, Pete Riccardella, and Glenn A. White, PWR Reactor Vessel Alloy 600 Issues, ASME_Ch44_p001–026, 12/19/2009.

    Google Scholar 

  2. Richey Edward, Morton, David, S., Etien, Robert A, Young, George A, Bucinell Ronakld B, SCC initiation in Alloy 600 heat affected zones exposed to high temperature water, Corrosion/2008, 2008.

    Google Scholar 

  3. Aguilar, A, Albarran J L, Lopez, H F, Martinez, L, On the heat treatment and microstructure in the intergranular stress corrosion cracking response of alloy 600, International conference on hydrogen effects on materials behavior and corrosion deformation interactions, Moran WY, USA, 22–26 Sept. 2002, pp.73–740.

    Google Scholar 

  4. Casales, M, Salinas-Bravo V M, Martinez Villafance A, Gonzalez Rodriguez J G, Effect of heat treatment on the stress corrosion cracking of alloy 690, Materials Science and Engineering A, vol. 332, no. 1–2, 2002, pp.223–230.

    Article  Google Scholar 

  5. Kim H P, Hwang S S, Iim Y S, Kuk I H, Kim J S, Effect of microstructure on stress corrosion cracking of alloy 600 and alloy 690 in 40% NaOH, Metals and Materials, vol. 7, no., 2001, pp.55–59.

    Article  Google Scholar 

  6. Kim H P, Hwang S S, lim Y S, Kuk I H, Kim J S, Effect of heat treatment and chemical composition on caustic stress corrosion cracking of alloy 600 and alloy 690, Key Engineering Materials, vol. 183–187, no.2, 2000, pp.707–712.

    Article  Google Scholar 

  7. Raquet, O; Feron, D; Santarini, G; Boursier, J M, IGSCC of alloy 600 in PWR primary water influence of a cold worked layer on crack initiation, International Conference on Hydrogen Effects on Materials Behavior and Corrosion Deformation Interactions; Moran, WY; USA; 22–26 Sept. 2002, (2003) pp. 761–770.

    Google Scholar 

  8. Moshier, W C, Brown, C M, effect of cold work and processing orientation on stress corrosion cracking behavior of alloy 600, Corrosion, vol. 56, no. 3, 2000, pp. 307–320.

    Article  Google Scholar 

  9. Moshier W C, Brown C M, Effect of cold work and processing orientation on SCC behavior of alloy 600, Corrosion 99, san Antonio, TX, USA, 25–30 Apr. 1999 (1999) pp.17.

    Google Scholar 

  10. Raquet, O.; Santarini, G., Stress corrosion crack propagation rate of alloy 600 in the primary water of PWR. Influence of a cold worked layer, Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors, 9th, Newport Beach, CA, United States, Aug. 1–5, 1999 (1999), pp. 207–214.

    Google Scholar 

  11. Park, I G, primary water stress corrosion cracking behaviors in the shot peened alloy 600 TT steam generator tubings, Nuclear Engineering and Design, vol. 212, no. 1–3, 2002, pp.395–399.

    Article  Google Scholar 

  12. Nishikawa, Yoshito, Totsuka Nobuo, Influence of minor elements on primary water stress corrosion cracking of alloy 600, Corrosion/2005, Housten, TX, USA, 3–7 Apr. 2005, (2005), pp. 17.

    Google Scholar 

  13. Materials Reliability Program: Resistance of Alloys 690, 52 and 152 to primary water stress corrosion cracking (MRP-237, Rev.1): Summaries of findings from completed and ongoing test program since 2004, EPRI, Palo alto, CA: 2008. 1018130.

    Google Scholar 

  14. Pablo Gabriel Fazzini, Jose Luis Otegui, Experimental determination of stress corrosion crack rates and service lives in a buried ERW pipeline, International Journal of Pressure Vessels and Piping, 84 (2007) pp.739–748.

    Article  Google Scholar 

  15. Gary Was, University of Michigan, Private Communication, 2011.

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Editor information

Editors and Affiliations

Rights and permissions

Reprints and permissions

Copyright information

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

About this paper

Cite this paper

Cao, G., Firouzdor, V., Allen, T. (2011). Stress Corrosion Cracking of Austenitic Alloys in Supercritical 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_115

Download citation

Publish with us

Policies and ethics