Advertisement

SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water

  • Peter L. AndresenEmail author
  • Martin M. Morra
  • Kawaljit Ahluwalia
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)

Abstract

Extensive SCC growth rate measurements have been performed on Alloy 690 and its weld metals in the past, and this paper focuses on SCC growth rate evaluation of Alloy 52/152 welds with a variety of defects and/or weld repairs, and in the dilution zone. Ductility dip cracking dominated the weld defects, and weld repair mockups were fabricated by EPRI Charlotte to be 20% or 50% excavation and repair, as well as welds with a refuse pass every layer. Only low and very low SCC growth rates were observed in all cases. Studies on weld dilution zone effects of varying Cr content were evaluated using welds created with variable ratios of dual-filler-wire feel, which permits definitive SCC growth rate measurements in a homogenous weld without the ambiguity of having the crack front in undefined composition of an actual weld dilution zone.

Keywords

Alloy 52 Alloy 152 Alloy 52i Weld metal Weld defects Weld repairs Stress corrosion cracking Crack growth rate High temperature water 

References

  1. 1.
    P.L. Andresen, Perspective and direction of stress corrosion cracking in hot water, in Proceedings of 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, NACE, 2001Google Scholar
  2. 2.
    P.L. Andresen, T.M. Angeliu, L.M. Young, Immunity, Thresholds, and Other SCC Fiction (TMS, Proc. Staehle Symp. on Chemistry and Electrochemistry of Corrosion and SCC, 2001)Google Scholar
  3. 3.
    P.L. Andresen, L.M. Young, P.W. Emigh, R.M. Horn, Stress corrosion crack growth rate behavior of Ni alloys 182 and 600 in high temperature water, corrosion/02, paper 02510, NACE, 2002Google Scholar
  4. 4.
    P.L. Andresen, Conceptual similarities and common predictive approaches for SCC in high temperature water systems, paper 96258, corrosion/96, NACE, 1996Google Scholar
  5. 5.
    F.P. Ford, P.L. Andresen, Corrosion in nuclear systems: environmentally assisted cracking in light water reactors, in Corrosion Mechanisms, ed. By P. Marcus and J. Ouder, Marcel Dekker, pp. 501–546, 1994Google Scholar
  6. 6.
    P.L. Andresen, C.L. Briant, Environmentally Assisted Cracking of Types 304L/316L/316NG Stainless Steel in 288 ℃ Water. Corrosion 45, 448–463 (1989)CrossRefGoogle Scholar
  7. 7.
    P.L. Andresen, Environmentally assisted growth rate response of nonsensitized AISI 316 grade stainless steels in high temperature water. Corrosion. 44 (7), 450 (1988)CrossRefGoogle Scholar
  8. 8.
    P.L. Andresen, J. Hickling, PWSCC growth rates of cold worked alloy 690, Conference on Alloy 600, Santa Ana Pueblo, NM, March 2005, EPRI, Palo AltoGoogle Scholar
  9. 9.
    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 1010269Google Scholar
  10. 10.
    P.L. Andresen, M.M. Morra, Materials reliability program: Resistance of alloy 690/52/152 to SCC crack growth in simulated PWR Primary Water (MRP-196), EPRI, Palo Alto, CA, 2006, Technical report 1013516Google Scholar
  11. 11.
    P.L. Andresen, M.M. Morra, K. Ahluwalia, Effect of deformation temperature, orientation and carbides on SCC of alloy 690, in Proceedings of 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013Google Scholar
  12. 12.
    P.L. Andresen, M.M. Morra, K. Ahluwalia, SCC of alloy 152/52/52i weld metals in PWR primary water, in Proceedings of 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013Google Scholar
  13. 13.
    P.L. Andresen, Overview and Perspective on Stress Corrosion Cracking of Alloy 690 and Alloy 152/52 Weld Metals, Report 3002009966 (EPRI, Palo Alto, 2017)Google Scholar
  14. 14.
    P.L. Andresen, M.M. Morra, K. Ahluwalia, SCC of alloy 690 and its weld metals, in Proceedings of 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, The Metallurgical Society, Aug 2011CrossRefGoogle Scholar
  15. 15.
    P.L. Andresen, M.M. Morra, K.S. Ahluwalia, J. Wilson, Effect of deformation and orientation on SCC of Alloy 690, in Proceedings of 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, American Nuclear Society, Aug 2009Google Scholar
  16. 16.
    P.L. Andresen, M. M. Morra, J. Hickling, K.S. Ahluwalia, J.A. Wilson, PWSCC of alloys 690, 52 and 152, in Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Canadian Nuclear Society, Aug 2007Google Scholar
  17. 17.
    P.L. Andresen, The Present and Future of SCC Testing of Alloy 690 and Its Weld Metals, Alloy 690 Experts Meeting (EPRI, Tampa, 2009)Google Scholar
  18. 18.
    P.L. Andresen, SCC of Alloy 690 Base Metal and HAZ in PWR Primary Water and of Alloy 52 & 152 Weld Metals in PWR Primary Water, Alloy 690 Experts Mtg (EPRI, Tampa, 2010)Google Scholar
  19. 19.
    M.B. Toloczko, S.M. Bruemmer, Crack Growth Response of alloy 690 in simulated PWR Primary Water, in Proceedings of 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, American Nuclear Society, Aug 2009Google Scholar
  20. 20.
    M.B. Toloczko, M.J. Olszta, N.J. Overman, S.M. Bruemmer, observations and implications of intergranular stress corrosion crack growth of alloy 152 weld metals in simulated PWR primary water, in Proceedings of 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013Google Scholar
  21. 21.
    S.M. Bruemmer, M. Olszta, M.B. Toloczko, Microstructural effects on stress corrosion crack growth in cold-worked alloy 690 tubing and plate materials, in Proceedings 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013Google Scholar
  22. 22.
    M.B. Toloczko, M.J. Olszta, S.M. Bruemmer, 1D cold rolling effects on SCC growth in alloy 690 tubing and plate materials and SCC crack growth testing of alloy 52 M in simulated PWR Primary Water, in Proceedings of 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, The Metallurgical Society, Aug 2011Google Scholar
  23. 23.
    D.J. Paraventi, W.C. Moshier, Alloy 690 SCC growth rate testing, in Workshop on Cold Work in Iron- and Nickel-Base Alloys, ed. by R.W. Staehle, J. Gorman, June 2007, EPRI, Palo AltoGoogle Scholar
  24. 24.
    D.J. Paraventi, W.C. Moshier, Alloy 690 SCC growth rate testing, in Proceedings of EPRI Alloy 690 Workshop, Atlanta, 31 Oct 2007Google Scholar
  25. 25.
    B. Alexandreanu, O. K. Chopra, W.J. Shack, The stress corrosion cracking behavior of alloys 690 and 152 weld in a PWR environment, PVP2008-61137, in Proceedings of ASME PVP, 2008Google Scholar
  26. 26.
    B. Alexandreanu, The stress corrosion cracking behavior of alloys 690 and 152 weld in a PWR environment, in Proceesings of 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, American Nuclear Society, Aug 2009Google Scholar
  27. 27.
    D. Tice, Personal communication on crack growth rate of alloy 690, AMEC (Serco), April 2010Google Scholar
  28. 28.
    D. Tice, S. Medway, N. Platts, J. Stairmand, I. Armson, Crack growth testing of cold worked alloy 690 in primary water environment, in Proceedings of 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, The Metallurgical Society, Aug 2011Google Scholar
  29. 29.
    D. Gomez-Briceno et al., “CGR testing of alloy 690 and weld metals 52 and 152”, alloy 690 experts meeting (EPRI, Tampa, 2010)Google Scholar
  30. 30.
    A.R. Jenks, G.A. White, P. Crooker, Assessment of laboratory PWSCC crack growth rate data for Nickel-based alloys, in International Light Water Reactor Materials Reliability Conference and Exhibition 2016, 1–4 Aug 2016, EPRI, Palo Alto, 2016. (and final EPRI report, in press)Google Scholar
  31. 31.
    ASME boiler and pressure vessel code, Sections III and XI, ASME, NYGoogle Scholar
  32. 32.
    M.J. Esmacher, SCC of industrial utilities: Boiler and cooling water systems, in Stress Corrosion Cracking: Mechanisms, Materials and Application to Industrial Problems, eds. by V.S. Raja, T. Shoji, Woodhead Publishing, 2010Google Scholar
  33. 33.
    P.L. Andresen, P.W. Emigh, M.M. Morra, R.M. Horn, Effects of yield strength, corrosion potential, stress intensity factor, silicon and grain boundary character on the SCC of stainless steels, in Proceedings of 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, ANS, 2003Google Scholar
  34. 34.
    P.L. Andresen, M.M. Morra, SCC of stainless steels and Ni alloys in high temperature water. Corrosion 64, 15–29 (2008)CrossRefGoogle Scholar
  35. 35.
    P.L. Andresen, G.S. Was, SCC of unirradiated stainless steels and Nickel alloys in hot water, in 17th International Corrosion Congress, Las Vegas, NACE, Houston, 2008Google Scholar
  36. 36.
    M.M. Morra, M. Othon, E. Willis, S. McCracken, “Characterization of Structures and Strains in 52-type and 152 Welds”, Alloy 690/52/152 PWSCC Research Collaboration Meeting (Tampa, Florida, 2011)Google Scholar
  37. 37.
    T.M. Angeliu, P.L. Andresen, J.A. Sutliff and R.M. Horn, intergranular stress corrosion cracking of unsensitized stainless steels in BWR Environments, in Proceedings of 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, AIME, 1999Google Scholar
  38. 38.
    T.M. Angeliu, P.L. Andresen, E. Hall, J.A. Sutliff, S. Sitzman, Strain and microstructure characterization of austenitic SS weld HAZs”, Corrosion/2000, Paper 00186, NACE, 2000Google Scholar
  39. 39.
    J.A. Sutliff, An investigation of plastic strain in copper by automated-EBSP, Microsc. Microanal. 5(Supp. 2), 236 (Proc: Microscopy & Microanalysis ‘99) (1999)Google Scholar
  40. 40.
    M.A. Othon, M.M. Morra, EBSD characterization of the deformation behavior of alloy 182 weld metal, Microscopy and Microanalysis, 11(Suppl 2), 522–523CD Cambridge University Press, (2005). doi: https://doi.org/10.1017/S1431927605506949
  41. 41.
    G.A. Young, M.J. Hackett, J.D. Tucker, T.E. Capobianco, Welds for Nuclear Systems, Comprehensive Treatise on Materials for Nuclear Systems, ed. by R. Konings, Editor in Chief (Elsevier Science, to be published in 2011)Google Scholar
  42. 42.
    P.L. Andresen, C.L. Briant, Role of S, P and N segregation on intergranular environmental cracking of stainless steels in high temperature water, in Proceedings of 3rd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, AIME, pp. 371–382, 1988Google Scholar
  43. 43.
    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)Google Scholar
  44. 44.
    P.L. Andresen, J. Hickling, K.S. Ahluwalia, J.A. Wilson, Effects of hydrogen on SCC growth rate of Ni alloys in high temperature water. Corrosion 64(9), 707 (2008)CrossRefGoogle Scholar
  45. 45.
    P.L. Andresen, J. Hickling, K.S. Ahluwalia, J.A. Wilson, effects of PWR Primary Water Chemistry on PWSCC of Ni alloys, in Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Canadian Nuclear Society, Aug 2007Google Scholar
  46. 46.
    S.A. Attanasio, D.S. Morton, Measurement of the Ni/NiO transition in Ni–Cr–Fe alloys and updated data and correlation to quantify the effect of aqueous hydrogen on primary water SCC, in Proceedings 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, ANS, 2003Google Scholar
  47. 47.
    L.W. Niedrach, A new membrane type pH sensor for use in high temperature high pressure water. J. Electrochem. Soc. 127, 2122 (1980)CrossRefGoogle Scholar
  48. 48.
    Elaine West, D.S. Morton, John Mullen, Bob Etien and Heather Mohr, SCC behavior of EN52/EN52i in deaerated water, in Proceedings of 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013Google Scholar
  49. 49.
    BWR vessel and internals project, evaluation of crack growth in BWR stainless steel RPV internals (BWRVIP-14-A), EPRI Report TR-105873, Mar 1996Google Scholar
  50. 50.
    S.M. Bruemmer, Unpublished data (Pacific Northwest Nat, Lab, 2016)Google Scholar
  51. 51.
    G. White, Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of thick-wall alloy 600 materials, MRP-55 Revision 1, Final Report 1006695, EPRI (Palo Alto, CA, 2002)Google Scholar
  52. 52.
    Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Welds (MRP-115), EPRI Final Report 1006696, Nov 2004Google Scholar
  53. 53.
    P.L. Andresen, SCC of high Cr alloys in BWR environments, in Proceedings of 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, The Metallurgical Society, Aug 2011CrossRefGoogle Scholar

Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  • Peter L. Andresen
    • 1
    Email author
  • Martin M. Morra
    • 2
  • Kawaljit Ahluwalia
    • 3
  1. 1.Andresen Cons.BakersfieldUSA
  2. 2.GE ResearchSchenectadyUSA
  3. 3.EPRIPalo AltoUSA

Personalised recommendations