Abstract
The stress corrosion cracking behavior of dissimilar metal (DM) welds, including Alloy 52-A 508 and Alloy 82-A 508, under simulated BWR coolant conditions was studied. Effects of postweld heat treatment and specimen size on the corrosion fatigue and SCC growth rates of DM welds were evaluated. The crack growth rates of the DM weld heat-treated at 621 °C for 24 h was observed to be faster than those for the as-welded. But the DM weld heat-treated at 621 °C for 8 h + 400 °C for 200 h showed better SCC resistance than the as-welded. The longer the heat treatment at 621 °C, the higher the chromium carbides density along the grain boundary was observed. The SCC growth rates observed for the 1/2T CT specimens were faster than those for 1T CT specimens. It could be accounted for by the shorter distance for oxygen and anions to diffuse to the crack tip in the thinner specimen.
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P. Eesing, B. Forssgren, and R. Kilian, “Root cause failure analysis of defected J-Groove welds in steam generator drainage nozzles”, 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, pp. 813–819, 2005.
Q. Peng, T. Shoji, S. Ritter, and H. P. Seifert, “SCC behavior in the transition region of an Alloy 182-SA 508 Cl.2 dissimilar weld joint under simulated BWR-NWC conditions”: 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, pp. 589–599, 2005.
M. Itow, M. Kikuchi, and N. Tanaka, “The Influence of corrosion potential on SCC growth behavior of a deep crack in Alloy 182 in simulated BWR environment”: Proceedings of the 11 th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, edited by G. S. Was, L. Nelson, and P. King, pp. 1192–1201, 2003.
W. Bamford and J. Hall, “A Review of Alloy 600 cracking in operating nuclear plants: historical experience and future trends”: Proceedings of the 11 th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, edited by G. S. Was, L. Nelson, and P. King, pp. 1071–1081, 2003.
H. Xu, and S. Fyfitch, “Laboratory investigation of PWSCC of CRDM nozzle 3 and its J-groove weld on the Davis-Besse reactor vessel head”: 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, pp. 833–842, 2005.
S. Fyfitch, D. E. Whitaker, and M. L. Arey, “CRDM and thermocouple nozzle inspections at the Oconee nuclear station”: The 10 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, edited by F. Peter Ford, G. S. Was, and J. L. Nelson, Lake Tahoe, Nevada, Aug. 5–9, 2001.
O. K. Chopra, W. K. Soppet, and W. J. Shack, Effects of alloy chemistry, cold work, and water chemistry on corrosion fatigue and stress corrosion cracking of nickel alloys and welds, NUREG/CR-6721, ANL-01/07, 2001.
P. L. Andresen, L. M. Young, P. W. Emigh and R. M. Horn, Stress corrosion crack growth rate behavior of Ni alloys 182 and 600 in high temperature water, Corrosion, Paper No. 02510, 2002.
A. Jenssen, U. Morin, B. Bengtsson and C. Jansson, Crack propagation in stainless steels and nickel base alloys in a commercial operating BWR, The 7 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, published by NACE, edited by R. E. Gold, A. R. McIlree, and S. M. Bruemmer, Breckenridge, Colorado, Aug. 7–10, pp. 553–562, 1995.
D. J. Paraventi and W. C. Moshier, Assessment of the interaction of variables in the intergranular stress corrosion crack growth rate behavior of alloys 600, 82, and 182, The 13 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, Whistler, British Columbia, Aug. 19–23, 2007.
T. Sato and T. Shoji, “Effects of specimen size and thickness on CGR in high temperature waters”, The 11 International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, Stevenson, WA, Aug. 10–14, pp. 862–869, 2003.
M. Itow, M. Kikuchi, and S. Suzuki, “SCC crack growth rates of type 304 stainless steel at high K region in simulated BWR environment”, Corrosion, Paper No. 00221, 2000.
E. Richey, D. S. Morton, and W. C. Moshier, “Influence of specimen size on the SCC growth rate of Ni-alloys exposed to high temperature water”, Corrosion, Paper No. 06513, 2006.
P. L. Andresen, “K/Size effects on SCC in irradiated, cold worked and unirradiated stainless steel, The 11 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, Stevenson, WA, Aug. 10–14, pp. 870–886, 2003.
J. Y. Huang, J. J. Yeh, R. C. Kuo, and J. R. Hwang, “Effect of dynamic strain aging on fatigue crack growth behavior of reactor pressure vessel steels”, Mater. Sci. and Tech. 22, (2006), 944–954.
TECH NOTE, Measurement of Residual Stresses by the Hole-drilling Strain Gauge Method, TN-503-4, published by Measurements Group, INC.
J. Y. Huang, M. C. Young, S. L. Jeng, J. J. Yeh, J. S. Huang and R. C. Kuo, “Environmentally assisted cracking behavior of an RPV steels and weldments under high temperature water conditions”, The 13 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, Whistler, British Columbia, Aug. 19–23, 2007.
W. C. Chung, J. Y Huang, L. W. Tsay and C. Chen, “Microstructure and stress corrosion cracking behavior of the weld metal in Alloy 52-A 508 dissimilar welds”, Materials Transactions, Vol. 52, No. 1 (2011) pp. 12–19.
J. Y. Huang, R. F. Liu, M. F. Chiang, S. L. Jeng, J. S. Huang and R. C. Kuo, J. C. Wang, “Corrosion fatigue behavior of dissimilar metal weldments under nominal constant ΔK loading mode in a simulated BWR coolant environment”, Corr. Sci. 53 (2011), 2289–2298.
L. W. Tsay, M. C. Young, and C. Chen, “Fatigue crack growth behavior of Laser-processed 304 stainless steel in air and gaseous hydrogen”, Corr. Sci., 45 (2003), 1985–1997.
R. K. Shieu, C. T. Chang, M. C. Young and L. W. Tsay, “The effect of residual thermal stresses on the fatigue crack growth of Laser-surface-annealed AISI 304 stainless, Part 1: computer simulation, Mater. Sci. eng. A 364 (2004), 101–108.
L. W. Tsay, M. C. Young, and F. Y. Chou, C. Chen, and R. K. Shiue, “The effect of residual thermal stresses on the fatigue crack growth of Laser-annealed 304 stainless steels, Materials Chemistry and Physics, 88 (2004), 348–352.
A. Jenssen, C. Jansson, and J. Sundberg, “The Effect of hold time on the crack growth rate of sensitized stainless steel in high temperature water”, Proceedings of the 12 international conference on environmental degradation of materials in nuclear power system-water reactors, edited by T. R. Allen, P. J. King, and L. Nelson, pp. 157–166, 2005.
P. L. Andresen, “SCC testing and data quality consideration”, Proceedings of the 9 International Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, edited by S. Bruemmer, P. Ford, and G Was, pp. 411–420, 1999.
G. A. Young, R. A. Etien, M. J. Hackett, J. D. Tucker, and T. E. Capobianco, in: The 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, Virginia Beach, Virginia, Aug. 23–27, 2009.
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Huang, J.Y., Chiang, M.F., Kuo, R.C., Huang, J.S., Jeng, S.L. (2011). Stress Corrosion Cracking Behavior of Dissimilar Metal Weldments in High Temperature Water 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_67
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DOI: https://doi.org/10.1007/978-3-319-48760-1_67
Publisher Name: Springer, Cham
Online ISBN: 978-3-319-48760-1
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