References
- P.E. Macdonald, V.N. Shah, L.W. Ward, P.G. Ellison, Steam Generator Tube Failures, NUREG/CR, 1966, pp. 78-114, 6365.
- P. Tran, PWR Steam Generator Replacement Survey Results, EPRI, 2005, 1011259.
- B. Grimmel, U.S. Plant Experience with Alloy 600 Cracking and Boric Acid Corrosion of Light-water Reactor Pressure Vessel Materials, NUREG, 2005, pp. 9-13, 1823.
- Y.S. Lim, H.P. Kim, S.S. Hwang, Microstructural characterization on intergranular stress corrosion cracking of alloy 600 in PWR primary water environment, J. Nucl. Mater. 440 (2013) 46-54. https://doi.org/10.1016/j.jnucmat.2013.03.088
- Y.S. Yi, S.H. Eom, H.P. Kim, J.S. Kim, Nickel boride (NiB) as an inhibitor for an IGSCC of alloy 600 and its applicability, J. Nucl. Mater. 347 (2005) 151-160. https://doi.org/10.1016/j.jnucmat.2005.08.011
- Y.S. Lim, S.S. Hwang, S.W. Kim, H.P. Kim, Primary water stress corrosion cracking behavior of an alloy 600/182 weld, Corros. Sci. 100 (2015) 12-22. https://doi.org/10.1016/j.corsci.2015.06.005
- S.S. Hwang, Y.S. Lim, S.W. Kim, D.J. Kim, H.P. Kim, Role of grain boundary carbides in cracking behavior of Ni base alloys, Nucl. Eng. Tech. 45 (2013) 73-79. https://doi.org/10.5516/NET.07.2012.013
- S.S. Hwang, H.P. Kim, SCC analysis of alloy 600 tubes from a retired steam generator, J. Nucl. Mater. 440 (2013) 129-135. https://doi.org/10.1016/j.jnucmat.2013.04.061
- S.S. Hwang, H.P. Kim, D.H. Lee, U.C. Kim, J.S. Kim, The mode of stress corrosion cracking in Ni-base alloys in high temperature water containing lead, J. Nucl. Mater. 275 (1999) 28-36. https://doi.org/10.1016/S0022-3115(99)00111-7
- S.S. Hwang, H.P. Kim, Y.S. Lim, J.S. Kim, L. Thomas, Transgranular SCC mechanism of thermally treated alloy 600 in alkaline water containing lead, Corros. Sci. 49 (2007) 3797-3811. https://doi.org/10.1016/j.corsci.2007.03.040
- S.W. Kim, H.P. Kim, Electrochemical noise analysis of PbSCC of Alloy 600 SG tube in caustic environments at high temperature, Corros. Sci. 51 (2009) 191-196. https://doi.org/10.1016/j.corsci.2008.10.014
- B.S. Rho, H.U. Hong, S.W. Nam, Analysis of the intergranular cavitation of Nb-a 286 alloy in high temperature low cycle fatigue using EBSD technique, Scr. Mater. 43 (2000) 167-173. https://doi.org/10.1016/S1359-6462(00)00387-0
- M. McMurtrey, G. Was, L. Patrick, D. Farkas, Relationship between localized strain and irradiation assisted stress corrosion cracking in an austenitic alloy, Mater. Sci. Eng. A 528 (2011) 3730-3740. https://doi.org/10.1016/j.msea.2011.01.073
- K. Fukuya, H. Nishioka, K. Fujii, T. Miura, T. Torimaru, An EBSD examination of SUS316 stainless steel irradiated to 73 dpa and deformed at 593 K, J. Nucl. Mater. 417 (2011) 958-962. https://doi.org/10.1016/j.jnucmat.2010.12.301
- E. West, G. Was, A model for the normal stress dependence of intergranular cracking of irradiated 316 L stainless steel in supercritical water, J. Nucl. Mater. 408 (2011) 142-152. https://doi.org/10.1016/j.jnucmat.2010.11.012
- E.A. West, M.D. McMurtrey, Z. Jiao, G.S. Was, Role of localized deformation in irradiation-assisted stress corrosion cracking initiation, Metall. Trans. A 43 (2012) 136-146. https://doi.org/10.1007/s11661-011-0826-5
- T. Watanabe, An approach to grain boundary design for strong and ductile polycrystals, Res. Mechanica 11 (1984) 47-84.
- G. Palumbo, P. King, P. Lichtenberger, K. Aust, U. Erb, Grain boundary design and control for intergranular stress-corrosion resistance, Scr. Metall. Mater. 25(1991) 1775-1780. https://doi.org/10.1016/0956-716X(91)90303-I
- E.M. Lehockey, A.M. Brennenstuhl, I. Thompson, On the relationship between grain boundary connectivity, coincident site lattice boundaries, and intergranular stress corrosion cracking, Corros. Sci. 46 (2004) 2383-2404. https://doi.org/10.1016/j.corsci.2004.01.019
- V. Gertsman, S.M. Bruemmer, Study of grain boundary character along intergranular stress corrosion crack paths in austenitic alloys, Acta Mater. 49 (2001) 1589-1598. https://doi.org/10.1016/S1359-6454(01)00064-7
- J. Gorman, PWR Reactor Vessel Alloy 600 Issues', Companion Guide to the ASME Boiler & Pressure Vessel Code : Criteria and Commentary on Select Aspects of the Boiler & Pressure Vessel and Piping Codes, ASME press, 2009 (chapter 44).
- J. Harris, V. Moroney, J. Gorman, Pressurized Water Reactor Generic Tube Degradation predictions-U.S. Recirculating Steam Generators with Alloy 600TT and Alloy 690TT, EPRI, July 2003, 1003589.
- S.I. Baik, M.J. Olszta, S.M. Bruemmer, D.N. Seidmana, Grain-boundary structure and segregation behavior in a nickel-base stainless alloy, Scr. Mater. 66 (2012) 809-812. https://doi.org/10.1016/j.scriptamat.2012.02.014
- H. Kawamura, H. Hirano, Role of grain boundary characteristics in caustic IGA/SCC resistance of thermally-treated Alloy 690 and shot-peened Alloy 800, in: Proc. 9th 11th International Symposium on Environmental Degradation of Materials in Nuclear Power SystemeWater Reactors, 1999, pp. 601-610.
- C. Shoemaker, in: Proc.: Workshop on Thermally Treated Alloy 690 Tubes for Nuclear Steam Generators (NP-4665S-sr), EPRI, Palo Alto, CA, 1986.
- S.S. Hwang, H.P. Kim, D.H. Lee, U.C. Kim, J.S. Kim, Corrosion behavior of Ni-based alloys in lead-contaminated water, in: Proc. Contributions of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors, vol. 1, French Nuclear Energy Society, Societe Francaise d'Energie Nucleaire [SFEN], Fontevraud, France, 1998, pp. 403-415.
- T. Sakai, T. Senjuh, K. Aoki, T. Shigemitsu, Y. Kishi, Lead-Induced stress corrosion cracking of Alloy 600 and 690 in high-temperature water, in: Proc. 5th International Symposium on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, 1991, pp. 764-772.
- J.M. Larson, S. Floreen, Metallurgical factors affecting the crack growth resistance of a superalloy, Metall. Trans. A 8 (1977) 51-55. https://doi.org/10.1007/BF02677263
- H. Loyer Danflou, M. Marty, A. Walder, in: S.D. Antolovich, R.W. Stusrud, R.A. MacKay, D.L. Anton, T. Khan, R.D. Kissinger, D.L. Klarstrom (Eds.), Superalloys, the Minerals, Metals, and Materials Society, Warrendale, PA, 1992, pp. 63-72.
- H.U. Hong, I.S. Kim, B.G. Choi, M.Y. Kim, C.Y. Jo, The effect of grain boundary serration on creep resistance in a wrought nickel-based superalloy, Mat. Sci. Eng. A 517 (2009) 125-131. https://doi.org/10.1016/j.msea.2009.03.071
- G.H. Bishop, W.H. Hartt, G.A. Bruggeman, Grain boundary faceting of (1010) tilt boundaries in zinc, Acta Metall. 19 (1971) 37-46. https://doi.org/10.1016/0001-6160(71)90159-3
- T.E. Hsieh, R.W. Balluffi, Observations of roughening/de-faceting phase transitions in grain boundaries, Acta Metall. Mater. 37 (1989) 2133-2139. https://doi.org/10.1016/0001-6160(89)90138-7
- K.J. Kim, H.U. Hong, S.W. Nam, A study on the mechanism of serrated grain boundary formation in an austenitic stainless steel, Mater. Chem. Phys. 126 (2011) 480-483. https://doi.org/10.1016/j.matchemphys.2010.12.025
- A.K. Koul, G.H. Gessinger, On the mechanism of serrated grain boundary formation xn ni-based superalloys, Acta Metall. 31 (1983) 1061-1069. https://doi.org/10.1016/0001-6160(83)90202-X
- A. Stratulat, J.A. Duff, T.J. Marrow, Grain boundary structure and intergranular stress corrosion crackinitiation in high temperature water of a thermally sensitized austenitic stainless steel, observed in situ, Corros. Sci. 85 (2014) 428-435. https://doi.org/10.1016/j.corsci.2014.04.050
- E. West, G. Was, A model for the normal stress dependence of intergranular cracking of irradiated 316 L stainless steel in supercritical water, J. Nucl. Mater. 408 (2011) 142-152. https://doi.org/10.1016/j.jnucmat.2010.11.012
- B. Alexandreanu, Grain Boundary Deformation-induced Intergranular Stress Corrosion Cracking of Ni-16Cr-9Fe in 360oC Water, Ph. D. Thesis, University of Michigan, Ann Arbor, MI, 2002.
- R. Bandy, D. van Rooyen, Tests with Inconel 600 to Obtain Quantitative Stress Corrosion Cracking Data for Evaluating Service Performance, BNL-NUREG-31814, U.S. Nuclear Regulatory Commission, Washington, DC, 1983.
- G.P. Airey, The effect of carbon content and thermal treatment on the SCC behavior of Inconel Alloy 600 steam generator tubing, Corrosion 35 (1979) 129-136. https://doi.org/10.5006/0010-9312-35.3.129
- J.R. Crum, Effect of composition and heat treatment on stress corrosion cracking of Alloy 600 steam generator tubes in sodium hydroxide, Corrosion 38 (1982) 40-45. https://doi.org/10.5006/1.3577317
Cited by
- Investigation on the formation of grain boundary serrations in additively manufactured superalloy Haynes 230 vol.32, pp.3, 2018, https://doi.org/10.2351/7.0000112
- Effects of solution annealing on the precipitation of dendrite-like carbides during continuous cooling in Alloy 690 vol.15, pp.None, 2018, https://doi.org/10.1016/j.jmrt.2021.09.150