Abstract
Stress corrosion cracking (SCC) of wrought Alloy 600 and parent weld metals (Alloys 182/82) is a significant cause of failure in pressurized water reactors (PWR). Only a small number of welds fabricated from Alloy 82 are affected by PWSCC. Most of these welds were not thermally heat treated opposite to what is done in the French industrial practice. This paper describes constant load crack growth rate (CGR) tests on Alloy 82 with and without post weld heat treatment. Metallurgical examination of Alloy 82 was carried out using mainly Transmission Electron Microscopy. The heat treatment seems to be highly beneficial by decreasing the CGR. This result can be explained by the effect of thermal treatment on the precipitation in Alloy 82.
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References
G. Turluer, G. Cattiaux, B. Monnot, D. Emond, J. Reuchet, P. Chartier, “The French Regulatory Experience and Views on Nickel-Base Alloy PWSCC Prevention and Treatment”, NRC Conference, Proceedings of Conference on Vessel Penetration Inspection Cracking and Repairs, Gaithersburg, MD, September 29 – October 2 nd , 2003.
USNRC Information Notice 2000–17, “Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V. C. Summer,” Oct. 18, 2000; Suppl. 1, Nov. 16, 2000; Suppl. 2, Feb. 28, 2001.
G. Rao, G. Moffat, A. McIlree, “Metallurgical investigation of cracking in the reactor vessel alpha loop hot leg nozzle to pipe weld at the V. C. Summer station”, Proceedings of Fontevraud V, Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurised Water Reactors 23–27, September 2002, pp. 29–38.
R. S. Pathania, A. R. McIlree, J. Hickling, “Overview of primary water cracking of alloys 182/82”, Fontevraud V, Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurised Water Reactors 23–27, September 2002, pp 13–27.
Materials Reliability Program: Review of Stress Corrosion Cracking of Alloys 182 and 82 in PWR Primary Water Service (MRP-220). EPRI, Palo Alto, CA: 2007. 1015427.
Material Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139, Revision 1). EPRI, Palo Alto, CA: 2008. 1015009.
Materials Reliability Program Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Welds (MRP-115), EPRI, Palo Alto, CA: 2004. 1006696.
Yoshito Nishikawa, Nobuo Totsuka, Koji Arioka, “Influence of Temperature on PWSCC Initiation and Crack Growth Rate (Susceptibility) of Alloy 600 Weld Metals”, Corrosion NACE 2004, paper 04670.
W. J. Mills, “Fracture surface morphology of stress corrosion cracks in nickel-base welds”, Proceedings of the 12 th International Conference on Environmental Degradation of Materials in Nuclear Power System — Water Reactors — Edited by T.R. Allen, P.J. King, and L. Nelson TMS (The Minerals, Metals & Materials Society), 2005, pp 669–682.
D. J. Paraventi, W. C. Moshier, «The effect of cold work and dissolved hydrogen in the stress corrosion cracking of Alloy 82 and Alloy 182 weld metal», in Proceedings of the 12 th International Conference on Environmental Degradation of Materials in Nuclear Power System — Water Reactors, Edited by T.R. Allen, P.J. King, and L. Nelson, TMS, August 14–18, 2005, Salt Lake City, USA, pp 543–555.
D. J. Paraventi, W. C. Moshier, «Assessment of the interaction of variables in the intergranular stress corrosion crack growth rate behaviour of Alloy 600, 82 and 182”, in Proceeding of the 13 th Environmental Degradation of Materials in Nuclear power Systems, NACE-TMS-ANS, August 19–23, 2007, Whistler, Canada.
NISHIKAWA Satoru, HORII Yukihiko, IKEUCHI Kenji, “Effect of Chromium Content on Stress Corrosion Cracking Susceptibility of Shielded Metal Arc Weld Metals for 600 Type Alloy in High Temperature Pressurized Pure Water”, 溶接学会論文集 第 27 卷第 4 号 p. 278–286 (2009) (in Japanese).
13. F. Champigny, C. Amzallag, F. Chapellier, F. Vaillant, “Maintenance strategy of Inconel components in PWR primary system in France”, NRC Conference, Proceedings of Conference on Vessel Penetration Inspection Cracking and Repairs, Gaithersburg, MD, September 29 – October 2 nd , 2003.
P. Efsing, B. Forssgren, R. Kilian “Root cause failure analysis of defected J-groove welds in steam generator drainage nozzles”, Proceedings of 12 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors”, TMS 2005.
P. Scott, “Primary Water Stress Corrosion Cracking of Nickel-base Alloys”, Report for the OECD/NEA Stress Corrosion Cracking and Cable Ageing Project (2010).
G. A. White, N. S. Nordmann, J. Hickling, C. D. Harrington, “Development of crack growth disposition curves for primary water stress corrosion cracking (PWSCC) of Alloy 82, 182 and 132 weldments”, Proceedings of the 12 th International Conference on Environmental Degradation of materials in Nuclear Power System — Water Reactors, edited by T.R. Allen, P.J. King and L. Nelson, TMS (The Minerals, Metal & Materials Society), 2005.
R. Lindström, P. Lidar, and J. Lagerstrom, “Crack growth of Alloy 182 in a simulated primary side PWR environment”, Proceedings of the Eighth International Symposium on the Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, Amelia Island, August 10–14, 1997, p. 430.
W. H. Bamford, J. P. Foster, and R. S. Pathania, “An investigation of Alloy 182 stress corrosion cracking in simulated PWR environment”, Proceedings of the Ninth International Conference on Environmental degradation of Materials in Nuclear Power Systems — Water Reactors, TMS, Warrendale, PA, 1999, p. 279.
S. A. Attanasio, J. V. Mullen, J. W. Wuthrich, W. W. Wilkening, D. S. Morton, “Stress Corrosion Crack Growth Rates (SCCGRs) for Alloy 182 and 82 Welds”, Proceedings of the Conference on Vessel Penetration Inspection, Crack Growth and Repair, Gaithersburg, MD, September 29 – October 2nd, 2003, NUREG/CP-0191.
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Guerre, C., Duhamel, C., Sennour, M., Crépin, J., Le Calvar, M. (2011). SCC Crack Growth Rate of Alloy 82 in PWR Primary Water Conditions — Effect of a Thermal Treatment. 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_68
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DOI: https://doi.org/10.1007/978-3-319-48760-1_68
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