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SCC of High CR Alloys in BWR Environments

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

Abstract

The current generation of weld metals used in BWRs, Alloy 182 and 82, have shown significant susceptibility to SCC in the laboratory and/or the field. With the laboratory data showing less than a factor of two difference in crack growth rate between the ~15% Cr Alloy 182 and the ~20% Cr Alloy 82, it seems clear that Alloy 82 will not be sufficiently resistant for long term SCC resistance. The higher Cr weld metals, Alloy 52i and 52, have dramatically greater (>100X) resistance to SCC than the current generation of weld metals, and indeed exhibit remarkable resistance to high corrosion potential, high water impurity levels, and high stress intensity factor.

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References

  1. P.L. Andresen, “SCC of Alloy 182 and 82 Weld Metals in BWR Water”, Corrosion/10, NACE, Houston, 2010.

    Google Scholar 

  2. P.L. Andresen, M.M. Morra, J. Hickling, K.S. Ahluwalia and J.A. Wilson, “PWSCC Growth Rates of Alloy 690 and Its Weld Metals”, Paper 1685, Corrosion/08, NACE, Houston, 2008.

    Google Scholar 

  3. George A. Young, Robert A. Etien, Micah J. Hackett, Julie D. Tucker, and Thomas E. Capobianco, “Physical Metallurgy, Weldability and In-Service Performance of Nickel-Chromium Filler Metals Used in Nuclear Power Systems”, Proc. 14th Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 2009, ANS.

    Google Scholar 

  4. R.A. Etien III, G.A. Young, T.E. Capobianco, J.V. Mullen, S. Leveillee and P.C. Sander, “Development of a Corrosion Resistant and Highly Weldable Filler Metal For Use With Alloy 690”, Paper 08597, Corrosion/2008, NACE, Houston, TX, 2008.

    Google Scholar 

  5. G.A. Young, T.E. Capobianco, R. Etien III, J.V. Mullen, L.L. D’Amore and S. Leveillee, “Development of a Highly Weldable and Corrosion Resistant Ni-Cr Filler Metal”, Proc. 11th Environmental Degradation of Materials in Nuclear Power Systems, 2003, ANS.

    Google Scholar 

  6. P.L. Andresen, “Development of Advanced Testing Techniques to Quantify the Improved PWSCC Resistance of Alloy 690 and its Weld Metals (MRP-123)”, EPRI, Palo Alto, CA, 2004. Technical Report 1010269.

    Book  Google Scholar 

  7. P.L. Andresen, M.M. Morra, K.S. Ahluwalia and J. Wilson, “Effect of Deformation and Orientation on SCC of Alloy 690”, Proc. 14th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors”, American Nuclear Soc, 2009.

    Google Scholar 

  8. P.L. Andresen, M. M. Morra, J. Hickling, K.S. Ahluwalia and J.A. Wilson, “PWSCC of Alloys 690, 52 and 152”, Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors”, Canadian Nuclear Soc, August 2007.

    Google Scholar 

  9. P.L. Andresen, M.M. Morra and K. Ahluwalia, “SCC of Alloy 690 and Its Weld Metals”, Fontevraud 7, Avignon, France, September 2010.

    Google Scholar 

  10. P.L. Andresen, M.M. Morra, J. Hickling, A. Ahluwalia, J. Wilson, “Effect of Deformation and Orientation on SCC of Alloy 690”, Paper 4840, Corrosion/09, NACE, Houston, 2009.

    Google Scholar 

  11. M.B. Toloczko, S.M. Bruemmer, “Crack Growth Response of Alloy 690 in Simulated PWR Primary Water”, Proc. 14th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors”, American Nuclear Soc, August 2009.

    Google Scholar 

  12. M.B. Toloczko, S.M. Bruemmer, “Crack Growth Response of Alloy 152 and 52 Weld Metals in Simulated PWR Primary Water”, Proc. 14th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors”, American Nuclear Soc, 2009.

    Google Scholar 

  13. B. Alexandreanu, O. K. Chopra, and W. J. Shack, “The Stress Corrosion Cracking Behavior of Alloys 690 and 152 Weld in a PWR Environment”, PVP2008–61137, Proc. of ASME PVP, July 27–31, 2008, Chicago.

    Book  Google Scholar 

  14. B. Alexandreanu, “The Stress Corrosion Cracking Behavior of Alloys 690 and 152 Weld in a PWR Environment”, Proc. 14th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors”, American Nuclear Soc, August 2009.

    Google Scholar 

  15. D.J. Paraventi and W.C. Moshier, “Alloy 690 SCC Growth Rate Testing”, Workshop on Cold Work in Iron- and Nickel-Base Alloys, Ed. R.W. Staehle and J. Gorman, June 2007, EPRI, Palo Alto.

    Google Scholar 

  16. D.J. Paraventi and W.C. Moshier, “Alloy 690 SCC Growth Rate Testing”, Proc. EPRI Alloy 690 Workshop, Atlanta, October 31, 2007.

    Google Scholar 

  17. P.L. Andresen and C.L. Briant, “Environmentally Assisted Cracking of Types 304L/316L/316NG Stainless Steel in 288 °C Water,” Corrosion, Vol. 45, pp. 448–463, 1989.

    Article  Google Scholar 

  18. P.L. Andresen and C.L. Briant, “Role of S, P and N Segregation on Intergranular Environmental Cracking of Stainless Steels in High Temperature Water,” Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, AIME, pp. 371–382, 1988.

    Google Scholar 

  19. P.L. Andresen, “Environmentally Assisted Growth Rate Response of Nonsensitized AISI 316 Grade Stainless Steels in High Temperature Water,” Corrosion 44, 7, p. 450, 1988.

    Article  Google Scholar 

  20. P.L. Andresen, “The Effects of Aqueous Impurities on Intergranular Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel,” Final Report NP3384 Contract T115–3, EPRI, 1983. See also, “Innovations in Experimental Techniques for Testing in High Temperature Aqueous Environments,” Report No. 81CRD088, GE CRD, Schenectady, New York, 1981.

    Google Scholar 

  21. L.W. Niedrach, “A New Membrane Type pH Sensor for Use in High Temperature High Pressure Water”, J. Electrochem. Soc. 127, p. 2122, 1980.

    Article  Google Scholar 

  22. J. Hickling, “Materials Reliability Program Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Welds (MRP-115)”, Final Report 1006696, EPRI, Palo Alto, November 2004.

    Google Scholar 

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Author information

Authors and Affiliations

  1. GE Global Research Center, One Research Circle CE2513, Schenectady, NY, 12309, USA

    Peter L. Andresen

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  1. Peter L. Andresen
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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

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

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Andresen, P.L. (2011). SCC of High CR Alloys in BWR Environments. 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_16

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