Skip to main content
SpringerLink
Log in

Mechanistic Study on PWSCC of Ni Based Alloys Using Hump-SSRT Tests under Dry Hydrogen Gas Environment, Simulated Primary Water and Rapid Straining Electrode Test in Simulated Primary Water

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

  • 2965 Accesses

Abstract

Hump-SSRT tests of alloy 600 have been carried out under simulated primary water and dry hydrogen gas at the temperature ranging from 360 to 320°C and rapid straining electrode tests of nickel based alloys have been carried out under simulated primary water at 320°C with and without dissolved hydrogen (DH).

The followings are clarified in this study.

  1. 1)

    Intergranular (IG) cracking is observed not only under simulated primary water but also under dry hydrogen gas. Constant loading condition are needed to generate IG cracking under hydrogen gas and the activation energy of PWSCC is almost the same as activation energy of IG cracking under dry hydrogen gas.

  2. 2)

    Rapid repassivation of alloy 690 and slow repassivation of alloy 600 are observed under the condition without DH. Repassivation was not observed and only cathodic current is observed under the condition with DH. These cathodic current reaches a plateau value in a few seconds and the cathodic current of alloy 690 is about 1 /5 of alloy 600 and 132.

According to these results, it is strongly suggested that the basic mechanism of PWSCC is one kind of hydrogen embrittlement. However, more details of the role of corrosion, surface condition and loading condition should be clarified in future.

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. Electric Power Research Institute, Materials Reliability Program Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking of Thick-Wall Alloy 600 Materials, EPRI Report MRP 55, Rev.1, (2002)

    Google Scholar 

  2. W.Bamford and J. Hall, A Review of Alloy 600 Cracking in Operating Nuclear Plants Including Alloy 82 and 182 Weld Behavior, Proc. of ICONE12, 12 th Int. Conf. on Nuclear Engineering, April 25–29, Arlington, Virginia USA, (2004).

    Book  Google Scholar 

  3. Japan Nuclear Energy Safety Organization, Heisei 16 th annual report on the investigation about evaluation method for SCC growth rate of Ni based alloy, 05Kizaiho-0009(2005) [in Japanese]

    Google Scholar 

  4. T. Sawada, K. Okamoto, T. Terai, N. Sekimura, I. Kimura and N. Maeda, Roadmap on Research and Development Plans for the Safety of Nuclear Power Generation, Journal of the Atomic Energy Society of Japan,.48(2006),p.94[in Japanese]

    Google Scholar 

  5. D.W. Alley, A Regulatory Analysis and Perspective Regarding Degradation of Materials in Light Water Reactors, CORROSION/2011,(2011), Paper No.11198

    Google Scholar 

  6. N. Totsuka, Z. Szklaska-Smialowska, Effect of Electrode Potential on the Hydrogen-Induced IGSCC of alloy 600 in Aqueous Solution at 350 C, Corrosion,43(1987), p.734

    Article  Google Scholar 

  7. .M.M. Hall, D.M. Symons, Hydrogen Assisted Creep Fracture Model for Low Potential Stress Corrosion Cracking of Ni-Cr-Fe Alloys, Proc. of Chemistry and Electrochemistry of Stress Corrosion Cracking:A Symposium Honoring the Contributions of R.W. Staehle, edited by R.H. Jones, TMS(The Minerals, Metals & Materials Society), pp.447–466(2001)

    Google Scholar 

  8. P.M. Scott, M. Le Calvar, Some Possible Mechanisms of Intergranular Stress Corrosion Cracking of Alloy 600 in PWR Primary Water, Proc. of Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, edited by R.E, Gold and E.P. Simonen, TMS(The Minerals, Metals & Materials Society), pp.657–667 (1993)

    Google Scholar 

  9. P.M. Scott, An Overview of Internal Oxidation as A Possible Explanation of Intergranular Stress Corrosion Cracking of Alloy 600 in PWRs, Proc. of Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, edited by F.P. Ford, S.M. Bruemmer and G.S. Was, TMS(The Minerals, Metals & Materials Society), pp.3–13(1999)

    Google Scholar 

  10. G. S. Was, T. M. Angeliu and J. K. Sung, Deformation and Intergranulor Cracking Behavior of Ni-Cr-Fe Alloys at High Temperature, Alloy 600 Expert Meeting,April6~9, (1993), Airlie Conference Center, Airlie, Virginia.

    Google Scholar 

  11. M. M. Hall, Jr., Thermally Activated Low Temperature Creep and Primary Water Stress Corrosion Cracking of Ni Cr Fe Alloys, Alloy 600 Expert Meeting, April6~9, (1993), Airlie Conference Center, Airlie, Virginia.

    Google Scholar 

  12. P. L. Andresen and F. P. Ford, Materials Sci. and Eng., A103, p.167 (1988)

    Article  Google Scholar 

  13. D. M. Symons and A. W. Thompson, The Effect of Hydrogen on the Fracture of Alloy X750, Met. Trans. A, 27A (1996),p.1014

    Google Scholar 

  14. Douglas M. Symons, The effect of hydrogen on the fracture toughness of Alloy X750 at elevated temperatures, Journal of nuclear materials, 265(1999)pp.225–231

    Article  Google Scholar 

  15. D. M. Symons, G. A. Young and J.R. Scully, The Effect of Strain on the Trapping of Hydrogen at Grain-Boundary Carbides in Ni-Cr-Fe Alloys, Met. Trans. A, 32A (2001),p.369

    Article  Google Scholar 

  16. T. Shibata and R. W. Staehle, Application of High Speed Elongation Technique to Stress Corrosion Cracking of Fe-Cr-Ni Alloys, Proc. 5 th Int. Cong. Met. Corrosion, Tokyo, NACE, p.487 (1974)

    Google Scholar 

  17. S. Sakai, N. Totsuka, M. Kamaya and N. Nakajima, A study of evaluation method for life time of alloy 600 on primary water stress corrosion cracking, CORROSION/ 2001,(2001), Paper No.01134

    Google Scholar 

  18. N. Totsuka, E. Lunarska, G. Cragnolino and Z. S. Smialowska, Effect of hydrogen on the intergranular stress corrosion cracking of alloy 600 in high temperature aqueous environments, Corrosion,43(1987), p.505

    Article  Google Scholar 

  19. C. H. Shen and P. G. Shewmon, A mechanism for hydrogen-induced intergranular stress corrosion cracking in alloy 600, Met. Trans. A, 21A (1990),p.1261

    Article  Google Scholar 

  20. Japan Nuclear Safety Organization, Heisei 20th Annual Report on the Investigation about Evaluation Method for SCC Growth Rate of Ni based Alloy, 09Genkouhou-0013 (Nov./2009) [written in Japanese]

    Google Scholar 

  21. S. A. Attanasio and D. S. Morton, Measurement of Nickel/Nickel Oxide Transition in Ni-Cr-Fe alloys and Updated Data and Correlations to Quantify the Effect of Aqueous Hydrogen on Primary Water SCC, Proc. of 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Stevenson, WA, USA, Aug.10–14,p.143 (2003)

    Book  Google Scholar 

  22. N. Totsuka, Y. Nishikawa and Y. Kaneshima, Effect of strain rate on primary water stress corrosion cracking of fracture mode and crack growth rate of nickel alloy and austenitic stainless steel, Corrosion,61(2005), p.219

    Article  Google Scholar 

  23. N. Totsuka and T. Terachi, The similarity between inter granular cracking of alloy 600 in simulated primary water and high purity hydrogen gas at high temperature, CORROSION/2011, 0(2011), Paper No.11208

    Google Scholar 

  24. N. Totsuka and Z. Szklaska-Smialowska, Hydrogen induced IGSCC of two unsensitized austenitic stainless steels in high-temperature water, Corrosion,44(1988), p.124

    Article  Google Scholar 

Download references

Author information

Authors and Affiliations

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

    Nobuo Totsuka & Takumi Terachi

  2. TOKYU REIT Toranomon Bldg., Japan Nuclear Energy Safety Organization, 3-17-1 Toranomon, Minato-ku, Tokyo, 105-0001, Japan

    Kenichi Takakura

Authors
  1. Nobuo Totsuka
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Takumi Terachi
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Kenichi Takakura
    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

Totsuka, N., Terachi, T., Takakura, K. (2011). Mechanistic Study on PWSCC of Ni Based Alloys Using Hump-SSRT Tests under Dry Hydrogen Gas Environment, Simulated Primary Water and Rapid Straining Electrode Test in Simulated Primary 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_98

Download citation

Publish with us

Policies and ethics

Search

Navigation