Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: Part 1

Corrosion

Volumn 59, Issue 11, 2003, Pages 931-994

  Staehle, R W ^a   Gorman, J A ^b  

^a Dominion Engineering Inc ^*  (United States)

^b Dominion   (United States)

Author keywords

Alloy 600; Alloy 690; Alloy 800; Heat transfer crevices; Secondary side; Steam generator; Stress corrosion cracking; Water chemistry

Indexed keywords

HEAT TRANSFER; PRESSURIZED WATER REACTORS; STEAM GENERATORS; TUBING;

WATER CHEMISTRY;

STRESS CORROSION CRACKING;

ALLOY; HEAT TRANSFER; PRESSURIZED WATER REACTOR; STEAM GENERATING EQUIPMENT; STRESS CORROSION CRACKING;

EID: 0347504609     PISSN: 00109312     EISSN: None     Source Type: Journal    
DOI: 10.5006/1.3277522     Document Type: Article

References (402)

1. H. Coriou, L. Grall, V. Le Gall, S. Vettier, "Stress Corrosion Cracking of Inconel in High-Temperature Water" (Amsterdam: North Holland Publishing Co., 1960). p. 161-169.
2. M.R. Fleming, A. Turner, J. Gorman, R.W. Staehle, A.R. McIlree, "Review of Steam Generator Girth Weld Cracking," Proc. Int. Symp. on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1994), p. 394.
3. Proc. Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE International, 1984).
4. Proc. 2nd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1986).
5. Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G.J. Theus, J.R. Weeks (Warrendale, PA: TMS, 1988).
6. Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. D. Cubicciotti (Houston, TX: NACE, 1990).
7. Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1992).
8. Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: TMS, 1993).
9. Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Alrey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995).
10. Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997).
11. Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999).
12. Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. F.P. Ford, G. Was, L. Nelson (Houston, TX: NACE, 2002).
13. Int. Symp. on Contribution of Materials Investigation to the Resolution of Problems Encountered in PWR Plants (Paris, France: French Nuclear Energy Society, 1985).
14. Int. Symp. on Contribution of Materials Investigation to the Resolution of Problems Encountered in PWR Plants, Fontevraud II (Paris, France: French Nuclear Energy Society. 1990).
15. Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1994).
16. Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998).
17. R.M. Latanision, R.W. Staehle, "Stress Corrosion Cracking of Iron Nickel Chromium Alloys," in Fundamental Aspects of Stress Corrosion Cracking, NACE-1, eds. R.W. Staehle, A.J. Forty, D. van Rooyen (Houston, TX: NACE, 1969), p. 214.
18. R.W. Staehle, "Stress Corrosion Cracking of Fe-Cr-Ni Alloy Systems," in Theory of Stress Corrosion Cracking, ed. J.C. Scully (Brussels, Belgium: NATO Scientific Affairs Division, 1971), p. 222.
19. R.W. Staehle, "Occurrence of Modes and Submodes of SCC," in Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 135.
20. G. Theus, R.W. Staehle, "Review of Stress Corrosion Cracking and Hydrogen Embrittlement in the Austenitic Fe-Cr-Ni Alloys," in Stress Corrosion Cracking and Hydrogen Embrittlement of Iron-Based Alloys, NACE-5, eds. J. Hochmann, J. Slater, R.W. Staehle (Houston, TX: NACE, 1977), p. 845.
21. R.W. Staehle, J.A. Gorman, K.D. Stavropoulos, C.S. Welty, Jr., "Application of Statistical Distributions to Characterizing and Predicting Corrosion of Tubing in Steam Generators of Pressurized Water Reactors," in Life Prediction of Corrodible Structures, ed. R.N. Parkins (Houston, TX: NACE, 1994), p. 1,374.
22. J.M. Gras, "Stress Corrosion Cracking of Steam Generator Tubing Materials Review and Assessment," Parkins Symp. on Fundamental Aspects of Stress Corrosion Cracking, eds. S.M. Bruemmer, E.I. Meletis, R.H. Jones, W.W. Gerberich, F.P. Ford, R.W. Staehle (Warrendale, PA: TMS, 1992), p. 411.
23. T. Cassagne, A. Gelpi, "Crack Growth Rate Measurements on Alloy 600 Steam Generator Tubing in Primary and Hydrogenated AVT Water," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: TMS, 1993), p. 679.
24. Z. Szlarska-Smialowska, R.B. Rebak, "Stress Corrosion Cracking of Alloy 600 in High-Temperature Aqueous Solutions: Influencing Factors, Mechanisms, and Models," in Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 223.
25. N. Sridhar, G. Cragnolino, "Stress Corrosion Cracking of Nickel-Based Alloys," in Stress Corrosion Cracking: Materials Performance and Evaluation, ed. R.H. Jones (Materials Park, OH: ASM International, 1992), p. 131.
26. W.Z. Friend, Corrosion of Nickel and Nickel-Based Alloys (New York, NY: John Wiley, 1980).
27. Control of Corrosion on the Secondary Side of Steam Generators. eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996).
28. M.J. Partridge, ed., Proc. 1983 Workshop on Secondary-Side Stress Corrosion Cracking and Intergranular Corrosion of PWR Steam Generator Tubing, NP-4458 (Palo Alto, CA: EPRI, 1983).
29. M.J. Partridge, ed., Proc. 1984 Workshop on Secondary-Side Stress Corrosion Cracking and Intergranular Corrosion of PWR Steam Generator Tubing, NP-4478 (Palo Alto, CA: EPRI, 1984).
30. M.J. Partridge, ed., Proc. 1985 Workshop on Remedial Actions for Secondary-Side Intergranular Corrosion, NP-4929 (Palo Alto, CA: EPRI, 1985).
31. A.R. McIlree, ed., Proc. 1985 Workshop on Primary-Side Stress Corrosion Cracking of PWR Steam Generator Tubing, NP-5158 (Palo Alto, CA: EPRI, 1987).
32. M.J. Partridge, ed., 1987 EPRI Workshop on Secondary-Side Intergranular Corrosion Mechanisms, NP-5971 (Palo Alto, CA: EPRI, 1987).
33. A.A. Stein, A.R. McIlree, eds., Proc. 1983 Workshop on Primary-Side Stress Corrosion Cracking of PWR Steam Generator Tubing, NP-5498 (Palo Alto, CA: EPRI, 1987).
34. J.A. Gorman, M.J. Partridge, eds., Proc. 1987 Workshop on Mechanisms of Primary Water Intergranular Stress Corrosion Cracking, NP-5987M (Palo Alto, CA: EPRI, 1988).
35. J.A. Gorman, ed., PWSCC Remedial Measures Workshop, NP-6719 (Palo Alto, CA: EPRI, 1989).
36. U.E. Gustafsson, ed., Proc. Workshop on the Role of Sulfur Species on the Secondary-Side Degradation of Alloy 600 and Related Alloys, NP-6710M (Palo Alto, CA: EPRI, 1990).
37. D.B. Lowenstein, J.A. Gorman, eds., Proc. 1990 Workshop on Circumferential Cracking of Steam Generator Tubes, NP-7198M (Palo Alto, CA: EPRI, 1990).
38. M.J. Partridge, W.S. Zemitis, eds., Proc. 1991 Workshop on Secondary-Side Intergranular Corrosion Mechanisms, TR-101103 (Palo Alto, CA: EPRI, 1991).
39. E.S. Hunt, J.A. Gorman, eds., Proc. 1991 Workshop on PWSCC of Alloy 600 in PWRs. TR-100852 (Palo Alto, CA: EPRI, 1992).
40. M.J. Partridge, ed., Proc. 1992 Workshop on Secondary-Side IGA/SCC, TR-106546, held December 8-10 (Palo Alto, CA: EPRI, 1992).
41. J. Gilman, ed., Proc. EPRI Workshop on Directions for Research on Corrosion-Assisted Cracking Initiation, held September 23-25 (Palo Alto, CA: EPRI, 1992).
42. J.A. Gorman, E.S. Hunt, eds., Proc. 1992 Workshop on PWSCC of Alloy 600 in PWRs, TR-103345 (Palo Alto, CA: EPRI, 1993).
43. R.G. Ballinger, A.R. McIlree, J.P.N. Paine, eds., Proc. Specialist Meeting on Environmental Degradation of Alloy 600, TR-104898 (Palo Alto, CA: EPRI, 1994).
44. J.A. Gorman, ed., Proc. 1994 Workshop on Primary Water Stress Corrosion Cracking of Alloy 600 in PWRS, TR-105406 (Palo Alto, CA: EPRI, 1995).
45. S. Hunt, ed., Proc. 1997 Workshop on PWSCC of Alloy 600 in PWRs, TR-109138 (Palo Alto, CA: EPRI, 1997).
46. J. Daret, ed., "Inhibition of IGA/SCC on Alloy 600 Surfaces Exposed to PWR Secondary Water." vol. 1-3, TR-106212-VI (Palo Alto, CA: EPRI, 1997).
47. R.S. Pathania, A.R. McIlree, eds., 2000 Workshop on PWSCC of Alloy 600 in PWRs, TR-1000873 (Palo Alto, CA: EPRI, 2000).
48. Steam Generator Owners Group, Steam Generator Reference Book (Palo Alto, CA: EPRI, 1985).
49. Steam Generator Owners Group, Steam Generator Reference Book (Palo Alto, CA: EPRI, 1994).
50. W.T. Lindsay, "MULTEQ: What It Is and What It Can Do." in Control of Corrosion on the Secondary Side of Steam Generators. eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 567.
51. C.F. Baes, W.T. Lindsay, "Modeling the Formation of Variable-Composition Liquid or Solid Phases of MULTEQ." in Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 577.
52. J.H. Alexander, L. Lu, MULTEQ: Equilibrium of an Electrolytic Solution with Vapor Liquid Partitioning and Precipitation, vols. 1 and 2, NP-5561 (Palo Alto, CA: EPRI, 1990).
53. J.W. Pugh, J.D. Nisbet, J. Met, 188 (1950): p. 269.
54. J.R. Davis, ed., ASM Specialty Handbook. Stainless Steels (Materials Park, OH: ASM International, 1994).
55. "Specification for Alloy 600 Steam Generator Tubing," in Guidelines for PWR Steam Generator Tubing Specifications and Repair, vol. 1, NP-6743 (Palo Alto, CA: EPRI, 1991).
56. J.A. Gorman, Guidelines for PWR Steam Generator Tubing Specifications and Repair. vol. 2, rev. 1: "Guidelines for Procurement of Alloy 690 Steam Generator Tubing," TR-016743-V2R1 (Palo Alto, CA: EPRI, 1999).
57. B. Stellwag, N. Wieling, L. Stieding, "Corrosion Resistance of SG Tubing Materials Alloy 800 and Alloy 690-A Comparative Study," Proc. 2nd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1986), p. 301.
58. H.W. Pickering, J.N. Al-Khamas, "IR Voltage in Stress Corrosion and Crevice Corrosion: Alloy T-2205 Duplex Stainless Steel," Chemistry and Electrochemistry of Corrosion and Stress Corrosion Cracking: A Symposium Honoring the Contributions of R.W. Staehle, ed. R.H. Jones (Warrendale, PA: TMS, 2001), p. 319.
59. W.D. Warren, "Chloride-Bearing Cooling Water and the Stress Corrosion Cracking of Austenitic Stainless Steel," Proc. 15th Annual Industrial Waste Conf. (Lafayette, IN: Purdue University, 1960), p. 420.
60. A.J. Baum, M.W. Rootham, "Operating Strategies for Minimizing the Occurrence of Steam Generator ODSCC," Water Chemistry of Nuclear Reactor Systems, 7 (London, U.K.: British Nuclear Energy Society, 1996), p. 625.
61. R.W. Staehle, "Bases for Predicting the Earliest Penetrations Due to SCC for Alloy 600 on the Secondary Side of PWR Steam Generators," U.S. Nuclear Regulatory Commission, NUREGCR-6737 (2001 ).
62. R.W. Staehle, J.A. Gorman, "Status and Issues in Corrosion on the Secondary Side of Steam Generators," CORROSION/96, paper no. 122 (Houston, TX: NACE, 1996), p. 122/1.
63. N.B. Pilling, R.E. Bedworth, "The Oxidation of Metals at High Temperatures," presented at the Annual General Meeting, vol. XXIX, held March 8 (London, U.K.: American Institute of Metals, 1923), p. 529.
64. R.N. Parkins, ASTM STP 668, "Development of Strain-Rate Testing and Its Implications," Stress Corrosion Cracking: The Slow Strain Rate Technique, eds. G.M. Ugiansky, J.H. Payer (West Conshohocken, PA: ASTM International, 1979), p. 5.
65. R.N. Parkins, "Stress Corrosion Cracking of Low-Strength Ferritic Steels," in The Theory of Stress Corrosion Cracking in Alloys, ed. J.C. Scully (Brussels, Belgium: NATO Scientific Affairs Division, 1971), p. 167.
66. H. Takamatsu, T. Kitera, K. Arioka, "Corrosion Experience with the Secondary Side of Steam Generators in Japan," in Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 113.
67. A. Baum, "Relationships Between Stress Corrosion Cracking Tests and Utility Operating Experience," Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. F.P. Ford, S.M. Bruemmer, G.S. Was (Warrendale, PA: TMS, 1999), p. 611.
68. H. Takamatsu, K. Matsueda, E. Kadokami, K. Arioka, T. Tsuruta, S. Okamoto, T. Ueno, "Evaluation of SG Crevice Environment by Directly Sampled Method Using an On-Site Autoclave Facility," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society. 1992), p. 752.
69. D.R. Diercks, J.F. Hall, P.C. Bryant, R.H. Keefer, R.W. Staehle, B. Woodman, "Local Chemistry and Deposit Formation at Upper Bundle Free-Span Region," in Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 79.
70. J.P.N. Paine, "Operating Experience and Intergranular Corrosion of Inconel Alloy 600 Steam Generator Tubing," CORROSION/82, paper no. 204 (Houston, TX: NACE, 1982), p. 204/1.
71. S.J. Green, J.P.N. Paine, Nucl. Technol. 55 (1981): p. 10.
72. C.Y. Cheng, Steam Generator Tube Experience, NUREG-0886 (Washington, DC: U.S. Nuclear Regulatory Commission, 1982).
73. R. Varrin, Jr., Characterization of PWR Steam Generator Deposits, TR-106048 (Palo Alto, CA: EPRI, 1996).
74. K.D. Stavropoulos, J.A. Gorman, R.W. Staehle, C.S. Welty, Jr., "Selection of Statistical Distributions for Prediction of Steam Generator Tube Degradation," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1992), p. 731.
75. D.P. Rochester, R.W. Eaker, "Laboratory Examination Results from Oconee Nuclear Station Once-Through Steam Generator Tubes," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 639.
76. B. L. Dow, Jr., Steam Generator Progress Report, EPRI, rev. 14, TE-106365-R14 (Palo Alto, CA: EPRI, 1999).
77. R.L. Jones, Mater. Perform. 7 (1996): p. 63.
78. W.J. Singley, I.H. Welinsky, S.F. Whirl, "Stress Corrosion of Stainless Steel and Boiler Water Treatment at Shippingport Atomic Power Station," Proc. American Power Conf., vol. 14 (Chicago, IL: Illinois Institute of Technology, 1959), p. 748.
79. W. K. Kratzer, "Examination of an Inconel 600 Tube from N Reactor Steam Generator 6A," CORROSION/71, paper no. 6 (Houston, TX: NACE, 1971), p. 6/1.
80. H. Blanchet, H. Coriou, L. Grall, C. Mahieu, C. Otter, G. Turleur, "Historical Review of the Principal Research Concerning the Phenomena of Cracking of Nickel-Based Austenitic Alloys," Stress Corrosion Cracking and Hydrogen Embrittlement of Iron-Based Alloys, NACE-5, eds. R.W. Staehle, J. Hochmann, R.D. McCright, J.E. Slater (Houston, TX: NACE, 1977), p. 1,149.
81. W. Debray, L. Stieding, "Materials in the Primary Circuit of Water-Cooled Power Reactors," International Nickel Power Conf., paper no. 3, Lausanne, Switzerland (1972), p. 3/1.
82. G.N. Flint, B.A. Weldon, "Some Investigations into the Stress Corrosion Behaviour of Fe-Ni-Cr Alloys in High-Temperature Water," Conf. Cycle on Chemistry of Water and Aqueous Corrosion in Steam Generators (Conventional and Nuclear) (Ecuelles, France: Electricite de France, 1972), p. 17.
83. A.R. McIlree, H.T. Michels, Corrosion 33 (1977): p. 60.
84. G.O. Hayner, C.R. Frye, G.J. Theus, S.L. Harper, J. Moaba, J.P.N. Paine, "Examination of Tubes Removed from St. Lucie Unit I and Investigations of Causes of the Corrosion," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G.J. Theus, J.R. Weeks (Warrendale, PA: TMS, 1988), p. 449.
85. R. White, R. Lieder, H. Legally, R. Gold, T. McGee, W. McBrine, T. McKrell, T. Esselman, R. Ballinger, "Root Cause Analysis for Cr-02-03166. Evaluation of "D" Steam Generator Tube Cracking," NRC Files, Acc. no. ML023240493, dated 11/5/02 and Acc. no. ML023240512, dated 11/8/02 (Washington, DC: U.S. Nuclear Regulatory Commission).
86. B.L. Dow, Jr., "Steam Generator Progress Report," TR-106365-R13 (Palo Alto, CA: EPRI, 1997).
87. R. Boueke, "Operating Experience with Steam Generators," Siemens Service Report, no. 11 (December 1989).
88. M. Pourbaix, Atlas of Electrochemical Equilibria In Aqueous Solutions (Houston, TX: NACE: Brussels, Belgium: CEBELCOR. 1974).
89. W.C. Schroeder, A.A. Berk, A. Gabriel, J. Am. Chem. Soc. 59 (1937): p. 1,783.
90. G.J. Mulder, Schukundigre Verhandelinger en Onderzoekingen, vol. 3, Part 2, Bijdragen tot de Geschiedenls van Het Scherkungig Gebouden Water, H.A. Kramers, Rotterdam, 1857.
91. O. Apfel, Untersuchungen über die Lōslichkeit von Alkaliphosphaten Pfungtadt, Technischen Hochschule,"diss. to Buchdr. Von Gebr. Helene, Darmstadt, 1911.
92. A.P. Obuchoff and M.N. Michallowa, J. Appl. Chem. USSR 8 (1935): p. 1,149.
93. A.J. Panson, G. Economy, C. Liu, T.S. Bulischek, W.T. Lindsay, Jr., J. Electrochem. Soc. 7 (1975): p. 915.
94. M.I. Ravich, L.G. Shcherbakova, Izv. Sektor Fiz.-Khimicheskogo Analiza, Akad. Nauk SSSR 26 (1955): p. 248.
95. G. Economy, A.J. Panson, C. Liu, J.N. Esposito, W.T. Lindsay, Jr., "Sodium Phosphate Solutions at Boiler Conditions: Solubility, Phase Equilibria, and Interactions with Magnetite," Proc. Int. Water Conf. (Pittsburgh, PA: Engineers' Society of Western Pennsylvania, 1975), p. 161.
96. M.I. Ravich, L.F. Yastrebova, Russ. J. Phys. Chem. 6 (1961): p. 218.
97. M.I. Ravich, F.E. Borovaya, V. Ya, Ketkovich, Izv. Sektor Fiz.-Khimicheskogo Analiza, Akad. Nauk SSSR 22 (1953): p. 250.
98. M.I. Ravich, F.E. Borovaya, Izv. Sektor Fiz.-Khimicheskogo Analiza, Akad. Nauk SSSR 26 (1955): p. 229.
99. A. Seidell, W.F. Linke, eds., Solubilities of Inorganic and Metal Organic Compounds, 4th ed., vol. 11 (Washington, DC: American Chemical Society, 1965).
100. B. Wendrow, K.A. Kobe, Ind. Eng. Chem. 44 (1952): p. 1,439.
101. W. Marshall, "High-Temperature Aqueous Potassium and Sodium Phosphate Solutions-Two-Liquid-Phase Boundaries and Critical Phenomena, 275-400°C," ORNL-5842, Potential Applications for Steam Generators (Washington, DC; U.S. Department of Energy, 1981).
102. M.A. Cordovi, "Corrosion Considerations in Light Water-Cooled Nuclear Power Plants," International Nickel Power Conf., paper no. 7 (New York. NY: International Nickel, 1972), p. 35.
103. J. Pocock, Nucl. Technol. 55 (1981): p. 117.
104. S.F. Whirl, T.E. Purcell, "Protection Against Caustic Embrittlement by Coordinated Phosphate pH Control," Proc. of the 3rd Annual Water Conf. (Pittsburgh, PA: Engineers' Society of Western Pennsylvania, 1942), p. 45.
105. V.M. Marcy, S.L. Halstead, Combust. 1 (1964): p. 45.
106. S. Odar, "Control of Phosphate Wastage in Steam Generators," 1987 EPRI Workshop on Secondary-Side Intergranular Corrosion Mechanisms, NP-5971, ed. M.J. Partridge (Palo Alto, CA: EPRI, 1987), p. 3-7.
107. N. Pessall, A.B. Dunlap, D.W. Feldman, Corrosion 33 (1977): p. 130.
108. C.M. Chen, K. Aral, G.J. Theus, Computer Calculated Potential-pH Diagrams to 300°C, vols. 1-3, NP-3137 (Palo Alto, CA: EPRI, 1983).
109. HSC Chemistry, ver. 3 (Pori, Finland: Outokumpu Research Oy, A. Roine).
110. F.J. Pocock, J. Mater. Energy Syst. 1 (1979), p. 3.
111. J.B. Lumsden, S.L. Jeanjaquet, J.P.N. Paine, A. McIlree, "Mechanism and Effectiveness of Inhibitors for SCC in a Caustic Environment," Proc. of the 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Alrey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995), p. 317.
112. M.J. Partridge, "Titanium Dioxide Application Guidelines," EPRI, TR-108002 (Palo Alto, CA: EPRI, 1997).
113. P. Millett, "Steam Generator Degradation: Current Mitigation Strategies for Controlling Corrosion," Proc. of the CNRA/CSNI Workshop On Steam Generator Tube Integrity In Nuclear Power Plants, NUREG-CP-0154, ed. D.R. Diercks (Washington, DC: U.S. Nuclear Regulatory Commission, 1997), p. 151.
114. N. Higuchi, M. Ito, M. Nakamura, Y. Shiroyama, T. Matsui, "Overview of the Use of Ethanolamine in Mihama Unit 2," 1998 JAIF Int. Conf. on Water Chemistry in Nuclear Power Plants, Water Chemistry '98 (Kashiwazaki City, Niigata: Japan Atomic Industrial Forum, 1998), p. 599.
115. P.J. Millett, C.J. Wood, "Recent Advances in Water Chemistry Control at U.S. PWRs," 1998 JAIF Int. Conf. on Water Chemistry in Nuclear Power Plants: Water Chemistry '98 (Kashiwazaki City, Niigata: Japan Atomic Industrial Forum, 1998), p. 19.
116. R.N. Parkins, STP-970, "Synthetic Solutions and Environment Sensitive Fracture," in The Use of Synthetic Environments for Corrosion Testing, eds. P.E. Francis, T.S. Lee (West Conshohocken, PA: ASTM, 1988), p. 132.
117. J. Congleton, T. Shoji, R.N. Parkins, Corros. Sci. 25 (1985): p. 633.
118. N. Sumitani, T. Kusakabe, K. Onimura, S. Tokunaga, "IGA/SCC Behavior of Thermally Treated Alloy 690," Proc. 1989 EPRI Alloy 690 Workshop, NP-6750, ed. J.A. Gorman (Palo Alto, CA: EPRI, 1990), p. 3/23.
119. A. Kishida, "Preliminary pH Measurements in High-Temperature Simulated PWR Steam Generator Crevice Environments at an On-Site Model Boiler Facility," Proc. Symp. on Chemistry in High-Temperature Water, NP-6005 (Palo Alto, CA: EPRI, 1990), p. C3g.
120. P. Millett, "PWR Secondary Water Chemistry Guidelines-Revision 5," EPRI TR-102134-R5 (Palo Alto, CA: EPRI, 2000).
121. P.L. Andresen, Corros. Sci. 49 (1993): p. 714.
122. A. Kishida, H. Takamatsu, H. Kitamura, S. Isobe, K. Onimura, K. Artoka, T. Hattori, T. Arai, M. Sata, "The Causes and Remedial Measures of Steam Generator Tube Intergranular Attack in Japanese PWR," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G.J. Theus, J.R. Weeks (Warrendale, PA: TMS, 1988), p. 465.
123. H. Nagano, K. Yamanaka, K. Tokimasa, H. Miyuki, "Intergranular Attack Behavior and Mechanisms for Nickel-Based Alloys in Caustic Solutions at Elevated Temperatures," Environment-Induced Cracking of Metals, NACE-10, eds. R.P. Gangloff, M.B. Ives (Houston, TX: NACE, 1990), p. 407.
124. R.W. Staehle, "Development and Application of Corrosion Mode Diagrams," Parkins Symp. on Fundamental Aspects of Stress Corrosion Cracking, eds. S.M. Bruemmer, E.I. Meletis, R.H. Jones, W.W. Gerberich, F.P. Ford, R.W. Staehle (Warrendale, PA: TMS, 1992), p. 457.
125. T. Schwarz, V. Schneider, "Influence of SG Design and Water Chemistry on Sludge Accumulation in Siemens Steam Generators," EPRI Workshop on Sludge Management, TR10421 (Palo Alto, CA: EPRI, 1994).
126. B. Stellwag, N. Wieling, "Influence of Water Treatment on Corrosion Resistance of SG Tube Materials in Pressurized Water Reactors," CORROSION/86, NACE, paper no. 257 (Houston, TX: NACE, 1986), p. 257/1.
127. H. Schenk, "Experiences with Steam Generators in the Nuclear Power Station at Obrigheim Over 100,000 Hours of Operation," Proc. Int. Seminar on Assessing Structural Integrity of Steel Pressure Boundary Components (New York, NY: Elsevier, 1984), p. 59.
128. P. Weyermann, K. Kueffer, R. Haelg, "Review of Operational Experience with Nuclear Power in Switzerland," Nuclear Power Experience (Vienna, Italy: International Atomic Energy Agency, 1984), p. 121.
129. J.H. Hicks, N.J. Mravich, F.J. Pocock, "Nuclear Steam Supply System Water Chemistry Research," Proc. American Power Conf., vol. 33 (Chicago, IL: Illinois Institute of Technology, 1971), p. 790.
130. G.J. Theus, P.L. Daniel, "Corrosion in Steam Generating Systems," Proc. 8th Int. Brown Boveri Symp. on Corrosion in Power Generating Equipment, eds. M.O. Speidel, A. Atrens (New York, NY: Plenum Press, 1984), p. 185.
131. S.J. Green, J.P.N. Paine, "Steam Generator Materials-Experience and Prognosis," Proc. Int. Symp. on Environmental Degradation of Materials in Nuclear flower Systems-Water Reactors (Houston, TX: NACE, 1984), p. 53.
132. W.T. Lindsay, Jr., "Modeling of Salt Concentrations in Crevices," Proc. Support-Structure Corrosion in Steam Generators, NP-2791, eds. C.E. Shoemaker, D.A. Jones (Palo Alto, CA: EPRI, 1983), p. 11/1.
133. S.G. Sawochka, "A Review of Power Cycle Water Chemistry Specifications for Nuclear Steam Generators," Proc. American Power Conf., vol. 38 (Chicago, IL: Illinois Institute of Technology, 1976), p. 890.
134. M.J. Bell, J.C. Blomgren, J.M. Fackelmann, W.D. Fletcher, S.J. Green, W.A. Haller, D.J. Morgan, J.A. Mundis, D. Paul, S. Rothstein, S.G. Sawochka, R.G. Varsanik, "PWR Secondary Water Chemistry Guidelines," EPRI, NP-2704-SR (Palo Alto, CA: EPRI, 1982).
135. J.C. Blomgren, ed., PWR Secondary Water Chemistry Guidelines-Revision 1, EPRI NP-5056-SR (Palo Alto, CA: EPRI, 1987).
136. C.J. Wood, chair, "Interim PWR Secondary Water Chemistry Guidelines Revision Committee," TR-1012330 (Palo Alto, CA: EPRI, 1992).
137. C. Wood, ed., "Interim PWR Secondary Water Chemistry Recommendations for IGA/SCC Control," TR-101230 (Palo Alto, CA: EPRI, 1992).
138. P. Millett, "Steam Generator Degradation: Current Mitigation Strategies for Controlling Corrosion," Proc. CNRA/CSNI Workshop on Steam Generator Tube Integrity in Nuclear Power Plants, NUREG-CP-0154, ed. D.R. Diercks (Washington, DC: U.S. Nuclear Regulatory Commission, 1997), p. 151.
139. R.W. Staehle, J.A. Begley, A.K. Agrawal, F.H. Beck, J.B. Lumsden, A.S. Bigger, C.A. Davis, "Corrosion and Corrosion Cracking of Materials for Water-Cooled Reactors," Final Summary Report (January 1, 1975-December 31, 1977) (The Fontana Corrosion Center. The Ohio State University, 1977).
140. P.M. Scott, P. Combrade, "Review of Crack Propagation Processes in Alloy 600," Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 419.
141. T. Tsuruta, S. Okamoto, T. Kitera, H. Takamatsu, T. Matsunaga, "IGA/SCC Crack Propagation Rate Measurements on Alloy 600 SG Tubing and Evaluation of Crevice Environments Using a Sidestream Model Boiler," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE, 1995), p. 187.
142. P.J. Millett, G.E. Brobst, J. Riddle, "A Probabilistic Approach to Controlling Crevice Chemistry," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995), p. 663.
143. S.S. Choi, K. Fruzzetti, S.G. Sawochka, "PWR Molar Ratio Control Application Guidelines," vol. 1, Summary, TR-104811 (Palo Alto, CA: EPRI, 1995).
144. S.G. Sawochka, S.S. Choi, K. Fruzzetti, "Relationship Between Bulk and Local Chemistries (Hideout Return) in Molar Ratio Control and Non Molar Ratio Control," Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 601.
145. H. Kawamura, H. Hirano, M. Koike, M. Suda, "Inhibitory Effect of Boric Acid on Intergranular Attack and Stress Corrosion Cracking of Alloy 600 in High-Temperature Water," CORROSION/95, paper no. 408 (Houston, TX: NACE, 1995), p. 408/1.
146. A. Molander, P. Tarkpea, P.O. Andersson, L. Bjornkvist, "Studies of Titanium Additions to PWR Secondary Systems," Water Chemistry of Nuclear Reactor Systems, 7 (London, U.K.: British Nuclear Energy Society, 1996), p. 422.
147. R.W. Staehle, "Lifetime Prediction of Materials in Environment," Uhlig's Corrosion Handbook, 2nd ed., ed. R.W. Revie (New York, NY: John Wiley and Sons, 2000), p. 27.
148. R.W. Staehle, "Environmental Definition," Materials Performance Maintenance, eds. R.W. Revie, V.S. Sastri, M. Elboujdaini, E. Ghali, D.L. Piron, P.R. Roberge, P. Mayer (Ottawa, ON, Canada: Pergamon Press, 1991), p. 3.
149. J.B. Lumsden, G.A. Pollock, P.J. Millett, N. Torigoe, H. Takamatsu, "Effects of the Feedwater Sodium/Chloride Ration and Hydrazine on Crevice Chemistry," 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S. Bruemmer, P. Ford, G. Was (Warrendale, PA: TMS, 1999), p. 545.
150. J.B. Lumsden, G.A. Pollock, P.J. Stocker, P.J. Millett, C. Faunchon, "Hideout in Prototypic Tube/Tube Support Plate Heated Crevices," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 108.
151. J.B. Lumsden, G.A. Pollock, P.J. Millett, H. Takamatsu, "Hideout in Prototypic Tube/Tube Support Plate Heated Crevices Using Laboratory Feedwater and OHI-1 Blowdown," 1998 JAIF Int. Conf. on Water Chemistry in Nuclear Power Plants, Water Chemistry '98 (Kashiwazaki City, Niigata: Japan Atomic Industrial Forum, 1998), p. 449.
152. H. Kawamura, H. Hirano, "Estimation of Impurity Concentration Factor on Boiling Heat-Transfer Surface within Tube-Tube Support Plate Crevice Using Corrosion Potential Measurement Technique," 1998 JAIF Int. Conf. on Water Chemistry in Nuclear Power Plants. Water Chemistry '98 (Kashiwazaki City, Niigata: Japan Atomic Industrial Forum, 1998), p. 546.
153. O. deBouvier, B. Prieux, F. Vaillant, M. Bouchacourt, P. Lemaire, "Nickel Alloy Stress Corrosion Cracking in Neutral and Lightly Alkaline Sulfate Environments," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 695.
154. Y. Shoda, H. Takamatsu, E. Kadokami, K. Takami, R. Kamio, K. Arioka, T. Hattori, H. Ohta, S. Okamoto, "Crevice Chemistry Estimation from Bulk Water Chemistry," Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 499.
155. G.M.W. Mann, R. Castle, "Hideout and Return of Chloride Salts in Heated Crevices Prototypic of Support Plates in Steam Generator," EPRI, NP-5015 (Palo Alto, CA: EPRI, 1987).
156. P.J. Millett, J.M. Fenton, "A Detailed Model of Localized Concentration Processes in Porous Deposits of SG's," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park. IL: American Nuclear Society, 1992), p. 745.
157. Duke Power pHSC4, pH, and Conductivity Calculator. Duke Power, 2000.
158. P. Ollar, L. Viricel-Honorez, "Better Understanding Flow Restricted Environments from Hideout Return Analyses," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998), p. 465.
159. D. You, Y. Lefevre, D. Feron, "A Chemical Study of Concentration Processes in Steam Generator Crevices: Influence of Boron on the Hideout of Sodium, Aluminum, and Silicon," 1998 JAIF Int. Conf. on Water Chemistry in Nuclear Power Plants, Water Chemistry '98 (Kashiwazaki City, Niigata: Japan Atomic Industrial Forum, 1998), p. 443.
160. Baum, P.J. Prabhu, M.W. Rootham, N.L. Zupetic, "Development of Improved PWR Secondary Water Chemistry Guidelines," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 74.
161. P.J. Prabhu, "A Review of the Effects of Silica on Stress Corrosion Cracking of Steam Generator Tubes," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was [Warrendale, PA: TMS, 1999), p. 619.
162. M. Navas, D. Gomez-Briceno, M. Garcia-Mazario, A.R. McIlree, "The Inhibiting of Silicon Compounds an Caustic SCC of Alloy 600MA," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998), p. 417.
163. C.R. Bergen, Corrosion 41 (1985): p. 85.
164. B. Sala, P. Combrade, A. Gelpi, M. Dupin, "The Use of Tube Examinations and Laboratory Simulations to Improve the Knowledge of Local Environments and Surface Reactions in TSPs," Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. Mcllree (Houston, TX: NACE, 1996), p. 483.
165. B. Sala, K. Henry, A.M. Lancha, M. Dupin, P. Combrade, R. Erre, A. Gelpi, "Analysis of the Deposits and Surface Layers on Tubes Pulled from PWR French Steam Generators," Eurocorr '96 (Paris, France: Centre Francais de L'Anticorrosion, 1996), p. 14/1.
166. B. Sala, A. Gelpi, S. Chevalier, M. Dupin, "Complementary Investigations Concerning the Analysis of the Deposits and Underlying Surfaces Observed on French PWR Steam Generators Pulled Out Tubes," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998), p. 553.
167. P.V. Balakrishnan, "Hideout, Hideout Return, and Crevice Chemistry in Steam Generators," 13th Int. Conf. on Properties of Water and Steam, ed. P.R. Tremaine (Washington, DC: NRC Research Press, 2000), p. 858.
168. Phase Diagrams for Ceramists, 2nd ed. (Columbus, OH: The American Ceramic Society, 1975).
169. R. Varrin, Jr., "Characteristics of PWR Steam Generator Deposits," TR-106048 (Palo Alto, CA: EPRI, 1996).
170. A.M. Lancha, D. Gomez-Briceno, M. Garcia-Mazario, C. Mafflotte, "Characterization of Ringhals-3 TSP Crevice and Tube Deposits," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 27.
171. F. Cattant, M. Dupin, B. Sala, A. Gelpi, "Analyses of Deposits and Underlying Surfaces on the Secondary Side of Pulled Out Tubes from a French Plant," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1994), p. 469.
172. J.M. Boursier, M. Dupin, P. Gosset, Y. Rouillon, "Secondary-Side Corrosion of French PWR Steam Generator Tubing: Contribution of Surface Analyses to the Understanding of the Degradation Process," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 555.
173. C. Goffin, R. Jadot, L. Duvivier, "Simulation of the Concentration Process in a Secondary-Side Steam Generator Crevice," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998), p. 441.
174. F.W. Pement, I.L.W. Wilson, R.G. Aspden, Mater. Perform. 19 (1980): p. 43.
175. C. Laire, G. Platbrood, J. Stubbe, "Characterization of the Secondary-Side Deposits of Pulled Steam Generator Tubes," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. Mcllree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995), p. 387.
176. J. Daret, T. Cassagne, Y. Lefevre, T.Q. Tran, "Evidence for the Reduction of Sulfates under Representative SG Secondary-Side Conditions, and for the Role of Reduced Sulfates on Alloy 600 Tubing Degradation," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 567.
177. Nucl. News 25 (1982): p. 47.
178. R. Bandy, R. Roberge, R.C. Newman, Corrosion 39 (1983): p. 391.
179. T. Sakai, S. Okabayashi, K. Aoki, K. Matsumoto, F. Nakayasu, Y. Kishi, "Effect of Reduced Sulfur on High-Temperature Aqueous Corrosion for Alloy 600," Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. D. Cubicciotti (Houston, TX: NACE, 1990), p. 12/37.
180. B. Sala, P. Combrade, R. Erre, R. Benoit, M. Le Calvar, "Chemistry of Sulfur in High-Temperature Water Reduction of Sulfates," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1992), p. 39.
181. W.E. Allmon, P.L. Daniel, S.J. Potterton, "Conditions for the Chemical Reduction of Sulfates in an Aqueous Environment," Proc. Workshop on the Role of Sulfur Species on the Secondary-Side Degradation at Alloy 600 and Related Alloys, NP-6710-SD, ed. U. E. Gustafsson (Palo Alto, CA: EPRI, 1990), p. 10/1.
182. P.A. Sherburne, "OTSG Materials Performance-25 Years Later," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998), p. 529.
183. D.P. Rochester, R.W. Eaker, B.B. Lowrey, "Results of Laboratory Examinations of Tubes from Oconee Nuclear Station Once-Through Steam Generators," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998), p. 513.
184. D.P. Rochester, R.W. Eaker, "Laboratory Examination Results from Oconee Nuclear Station Once-Through Steam Generator Tubes," Proc. 9th, Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 639.
185. D.P. Rochester, "Laboratory Investigation of Free-Span Axial Corrosion in Oconee Nuclear Stations Once-Through Steam Generators," Water Chemistry of Nuclear Reactor Systems, 8 (London, U.K.: British Nuclear Energy Society, 2000), p. 1.
186. G. Economy, R.J. Jacko, F.W. Pement, Corrosion 43, 12 (1987): p. 727.
187. S.M. Dehmlow, "Development of Accelerated Test Methods: Application to a Fillett Welded Tube and Plate Geometry," Proc. 1994 Workshop on Primary Water Stress Corrosion Cracking of Alloy 600 in PWRs, TR 105406, ed. J.A. Gorman (Palo Alto, CA: EPRI, 1995), p. C4-7.
188. B.P. Miglin, J.M. Sarver, "Investigation of Lead as a Cause of Stress Corrosion Cracking at Support Plate Intersections," EPRI, NP-7367-S (Palo Alto, CA: EPRI, 1991).
189. P.J. Millett, "Theoretical and Experimental Investigation of Local Concentration Processes in PWR Steam Generators" (PhD thesis, The University of Connecticut, 1991).
190. P.J. Millett, J.P.N. Paine, J.M. Fenton, "The Role of Sludge and Fouling on Local Concentration Processes in PWR Steam Generators," Steam Generator Sludge Deposition in Recirculating and Once-Through Steam Generator Upper Tube Bundle and Support Plates, NE-vol. 8. eds. R.L. Baker, E.A. Harvego (New York, NY: ASME, 1992), p. 1.
191. P.J. Millett, J.M. Fenton, "A Detailed Model of Localized Concentration Processes in Porous Deposits of SGs," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1992), p. 745.
192. C. Fauchon, P.J. Millet, P.M. Rogers, M. McNeil, J.B. Lumsden, "Modeling Hideout Processes in Prototypical Tube/Tube Support Plate Heated Crevices," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998), p. 477.
193. C. Fauchon, P.J. Millett, P. Ollar, "Application of Modeling to Local Chemistry in PWR Steam Generators," 3rd Int. Steam Generator and Heat Exchanger Conf. (Toronto, Canada: Canadian Nuclear Society, 1998), p. 537.
194. G.R. Engelhardt, M. Urquidi-Macdonald, A. Sehgal, D.D. Macdonald, P.J. Millet, "Modeling Corrosion in Steam Generator Crevices under Heat-Transfer Conditions," Control of Corrosion on the Secondarv Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 551.
195. G. Engelhardt, M. Urquidi-Macdonald, J. Sikora, D.D. Macdonald, P.J. Millett, "A Mathematical Model for Localized Corrosion in Steam Generator Crevices under Heat-Transfer Conditions," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995), p. 423.
196. G.R. Engelhardt, D.D. Macdonald, P.J. Millett, Corros. Sci. 41 (1999): p. 2,165.
197. J.A. Savchik, M.S. Burke, "Integrated Modeling and Characterization of Local Crack Chemistry," Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 757.
198. R.H. Keefer, L.W. Keeton, "Computational Thermal Hydraulic Modeling of a Steam Generator and a Boiler Simulator Autoclave," Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 643.
199. D. Duncan, M. Lubert, S.J. Kast, "Three-Dimensional Hydraulic Analysis of Crevice Geometries," Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 529.
200. C.L. Fauchon, "Development and Testing of an Electrochemical Model for PWR Steam Generators Crevice Environment" (Master of Science in Nuclear Engineering thesis, Massachusetts Institute of Technology, 2000).
201. A.J. Baum, "Postulated Relationships Between Bulk Chemistry, Crevice Concentration, and Corrosion Processes," Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 711.
202. A.J. Baum, "Development of Improved PWR Secondary Water Chemistry Guidelines," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 74.
203. A.J. Baum, "Experimental Evaluation of Tube Support Plate Crevice Chemistry," Presentation to 2001 EPRI Plant Chemistry Meeting, held January 22, 2001.
204. A.J. Baum, "Restricted Geometries and Deposits," The ASME Handbook on Water Technology for Thermal Power Systems, ed. P. Cohen (New York, NY: ASME, 1989), p. 279.
205. A.J. Baum, "Relationships Between Stress Corrosion Cracking Tests and Utility Operating Experience," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 611.
206. A.J. Baum, "Experimental Evaluation of Tube Support Plate Crevice Chemistry," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. P. Ford, G. Was, L. Nelson (Houston, TX: NACE, 2002).
207. S.G. Bankoff, R.S. Tankin, "Boiling Heat Transfer in a Narrow Eccentric Annulus," EPRI. NP-2610 (Palo Alto, CA: EPRI, 1982 ).
208. R.W. Staehle, "Combining Design and Corrosion for Predicting Life," Life Prediction of Corrodible Structures, ed. R.N. Parkins (Houston, TX; NACE, 1994), p. 138.
209. R.W. Staehle, J.A. Gorman, "Development and Application of Intensity and Operating Diagrams for Predicting the Occurrence and Extent of Stress Corrosion Cracking," Corrosion Science and Engineering: Proc. Int. Symp. In Honor of Marcel Pourbaix's 85th Birthday, Rapports Techniques, vol. 157-158 (Brussels, Belgium: CEBELCOR, 1989), p. 199.
210. E. Pierson, C. Laire, "The Influence of Copper on the SCC of Alloy 600 and Alloy 690 Steam Generator Tubes." Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998), p. 381.
211. R.J. Jacko, "Stress Corrosion Testing of Candidate Steam Generator Materials," Proc. Workshop on Thermally Treated Alloy 690 Tubes for Nuclear Steam Generators, NP-4665S SR, ed. C.E. Shoemaker (Palo Alto, CA: EPRI, 1986), p. 15/1.
212. Ph. Berge, J.R. Donati, Nucl. Technol. 55 (1981): p. 88.
213. Ph. Berge, D. Noel, J. Gras, B. Prieux, "Chloride Stress Corrosion Cracking of Alloy 600 in Boric Acid Solutions," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 189.
214. H.R. Copson, S.W. Dean, Corrosion 21 (1965): p. 1.
215. D. Gomez-Briceno, M.L. Castano, "Inconel 690TT and Incoloy 800 in S, Cu, and Pb Environments." Proc. 1991 Workshop on Secondary-Side Intergranular Corrosion Mechanisms, TR101103, eds. M.J. Partridge, W.S. Zemitis (Palo Alto, CA: EPRI, 1991).
216. C.M. Brown, W.J. Mills, "Fracture Toughness, Tensile, and Stress Corrosion Cracking Properties of Alloy 600, Alloy 690, and Their Welds in Water," CORROSION/96, paper no. 90 (Houston, TX: NACE, 1996), p. 90/1.
217. P.M. Scott, P. Combrade, "On the Mechanisms of Secondary-Side PWR Steam Generator Tube Cracking." Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 65.
218. P. Combrade, O. Cayla, M. Foucault, D. Vancon, A. Gelpi, G. Slama, "About the Role of Surface Films on Alloy 600 Corrosion in High-Temperature Deaerated Environments," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G.J. Theus, J.R. Weeks (Warrendale, PA: TMS, 1988), p. 525.
219. P. Combrade, "The Role of Surface Films on the Control of Alloy 600 Corrosion in PWR Reactors-No Results, a Few Comments, a Lot of Questions," Proc. Specialist Meeting on Environmental Degradation of Alloy 600, TR-104898, eds. R.G. Ballinger, A.R. McIlree, J.P.N. Paine (Palo Alto, CA: EPRI, 1994).
220. I. Ohsaki, K. Onishi, Y. Ohkubo, T. Hattori, S. Tokunaga, "Study of the Improvement of Steam Generator Tubing and Tube Support Plate Materials," 2nd Int. Steam Generator and Heat Exchange Conf., ed. D.E. Anderson (Toronto, Canada: Canadian Nuclear Society, 1994), p. 8.93.
221. S. Tsujikawa, S. Yashima, "Results of Steam Generator Tubing Reliability Test," 2nd Int. Steam Generator and Heat Exchange Conf., ed. D.E. Anderson (Toronto, Canada: Canadian Nuclear Society, 1994), p. 6,73.
222. X.C. Jiang, R.W. Staehle, Corrosion 53 (1997): p. 869.
223. X.C. Jiang, R. W. Staehle, "Application of the Chemical-Mechanical Correlation Equation for Stress Corrosion Cracking," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 582.
224. R.W. Staehle, ASTM STP 1401. "Framework for Predicting Stress Corrosion Cracking," Environmentally Assisted Cracking: Predictive Methods for Risk Assessment and Evaluation of Materials, Equipment, and Structures, ed. R. Kane (West Conshohocken, PA: ASTM, 2000), p. 131.
225. M.E. Indig, A.R. McIlree, Corrosion 35 (1979): p. 31.
226. F.P. Ford, P.L. Andresen, "Corrosion in Nuclear Systems: Environmentally Assisted Cracking in Light Water Reactors," Corrosion Mechanisms in Theory and Practice, eds. P. Marcus, J. Oudar (New York, NY: Marcel Dekker, 1995), p. 501.
227. H.R. Copson, C.F. Cheng, Corrosion 13 (1957): p. 397.
228. H.R. Copson, "Effect of Stress Corrosion Cracking of Some Alloys Containing Nickel," Physical Metallurgy of Stress Corrosion Fracture, ed. T.N. Rhodin (New York, NY: Interscience, 1959), p. 247.
229. H.R. Copson, "Discussion on H. Coriou, L. Grall, P. Olivier, and H. Willermoz, 'Influence of Carbon and Nickel Content on Stress Corrosion Cracking of Austenitic Stainless Alloys in Pure or Chlorinated Water at 350°C' Fundamental Aspects of Stress Corrosion Cracking, NACE-1, eds. R.W. Staehle, A.J. Forty, D. van Rooyen (Houston, TX: NACE, 1969), p. 352." p. 358.
230. H.R. Copson, G. Economy, Corrosion 24 (1968): p. 55.
231. H. Coriou, L. Grall, M. Pelras, H. Willermoz, "Stress Corrosion Cracking of Chromium-Nickel-Iron Austenites in Alkaline Media at High Temperature," 8th Colloque de Metallurgie (Paris, France: Centre d'Etudes Nucleaires de Saclay, 1964), p. 135.
232. H. Coriou, A. Desestret, L. Grall, J. Hochmann, Corros. Anti-Corros. 14 (1966), p. 163-170.
233. H. Coriou, L. Grall, P. Olivier, H. Willermoz, "Influence of Carbon and Nickel Content on Stress Corrosion Cracking of Austenitic Stainless Alloys in Pure or Chlorinated Water at 350°C," Fundamental Aspects of Stress Corrosion Cracking, NACE-1. eds. R.W. Staehle, A.J. Forty, D. van Rooyen (Houston, TX: NACE. 1969), p. 352.
234. 3-HF Pickling on Stress Corrosion Cracking of Ni-Cr-Fe Alloy 600 in High-Purity Water at 660°F, WAPD-TM-944 (Pittsburgh, PA: Bettis Atomic Power Lab., 1970).
235. W. Hubner, B. Johnasson, M. de Pourbaix, Studies of the Tendency to Intergranular Stress Corrosion Cracking of Austenitic Fe-Cr-Ni Alloys in High-Purity Water at 300°C, AE-437 (Studsvik, Sweden: Aktiebolaget Atomenergi, 1971).
236. W. Hubner, M. de Pourbaix, G. Ostberg, "Stress Corrosion Cracking of Stainless Steels and Nickel-Based Alloys in Chloride-Containing Water and Steam at 200-300°C," Proc. 4th Int. Congress on Metallic Corrosion, ed. N.E. Hamner (Houston, TX: NACE, 1972), p. 65.
237. R.W. Staehle, A.J. Forty, D. van Rooyen, eds., Fundamental Aspects of Stress Corrosion Cracking, NACE- 1 (Houston, TX: NACE. 1969).
238. A.R. McIlree, H.T. Michels, Corrosion 33 (1974): p. 60.
239. H.R. Copson, D. van Rooyen, A.R. McIlree, "Stress Corrosion Behavior of Ni-Cr-Fe Alloys in High-Temperature Aqueous Solutions," 5th Int. Congress on Metallic Corrosion (Houston, TX: NACE, 1972), p. 376.
240. A.J. Sedriks, S. Floreen, A.R. McIlree, Corrosion 32 (1976): p. 157.
241. NRC Pipe Crack Study Group, "Investigation and Evaluation of Stress Corrosion Cracking in Piping of Light Water Reactor Plants," NUREG-0531 (Washington, DC: U.S. Nuclear Regulatory Commission, 1979).
242. P.L. Andresen, "Conceptual Similarities and Common Predictive Approaches for SCC in High-Temperature Water Systems," CORROSION/96, paper no. 258 (Houston, TX: NACE, 1996). p. 258/1.
243. N. Totsuka, Z. Szklarska-Smlalowska, "Hydrogen-Induced IGSCC of Ni-Containing FCC Alloys in High-Temperature Water," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G.J. Theus, J.R. Weeks (Warrendale, PA: TMS, 1988). p. 691.
244. B. Grönwall, L. Ljungberg, W. Hübner, W. Stuart, Nucl. Eng. Des. 6 (1967): p. 383.
245. E.S. Hunt, D.J. Gross, "PWSCC of Alloy 600 Materials in PWR Primary System Penetrations," TR-103696 (Palo Alto, CA: EPRI, 1994).
246. NRC Information Notice 2000-17, "Crack in Weld Area of Reactor Coolant System Hot Leg Piping at V.C. Summer" (Washington, DC: U.S. Nuclear Regulatory Commission, Oct, 18, 2000).
247. M.R. Robinson, "Oconee Unit 1 and Unit 3 Reactor Vessel Head Leakage," presentation by M.R. Robinson (Duke Power Company) to the U.S. NRC, http://www.nrc.gov (April 12, 2001).
248. T. Shoji, "Mechanics and Mechanisms of Stress Corrosion Cracking of Alloy 600 in High-Temperature Waters," Proc. Specialist Meeting on Environmental Degradation of Alloy 600, TR- 104898, eds. R.G. Ballinger, A.R. McIlree, J.P.N. Paine (Palo Alto, CA: EPRI, 1994), p. 18/ 1.
249. Z. Szklarska-Smialowska, Z. Xia, R. R. Valbuena, Corrosion 50 (1994): p. 76.
250. M.R. Fleming, A. Turner, J. Gorman, R.W. Staehle, "Review of Steam Generator Girth Weld Cracking." TR- 103498 (Palo Alto, CA: EPRI. 1993).
251. K. Norring, J. Engstrom, P. Norberg, "Intergranular Stress Corrosion Cracking in Steam Generator Tubing. Testing of Alloy 690 and Alloy 600 Tubes." Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G.J. Theus, J.R. Weeks (Warrendale. PA: TMS, 1988), p. 587.
252. A.J. Forty, P.H. Humble, "Surface Embrittlement and Stress Corrosion Cracking of Brass in a Tarnishing Solution," 2nd Int. Congress on Metallic Corrosion, ed. E.C. Greco (Houston, TX: NACE, 1966 ). p. 80.
253. B. Sala, M. Organista, K. Henry, R. Erre, A. Gelpi, F. Cattant, M. Dupin, "Laboratory Study of Corrosion of Steam Generator Tubes: Preliminary Results," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995), p. 259.
254. B. Sala, K. Henry, S. Chevalier, M. Organista, R. Erre, A. Gelpi, M. Dupin, F. Cattant, "Laboratory Study of the IGA/SCC in the Secondary Side of SG. Role of Silica Compounds," Eurocorr '96, Session IX, Nuclear Corrosion and Protection. Extended Abstracts (Nice, France: Centre Francais de L'Anticorrosion Societe de Chimie Industrielle, 1996), p. 10/ 1.
255. B. Sala, S. Chevalier, M. Organista, A. Gelpi, A. Stutzmann, M. Dupin, "Study of the Corrosion Process of the Secondary Side of Steam Generators: An Electrochemical Study." 1998 JAIF Int. Conf. on Water Chemistry in Nuclear Power Plants, Water Chemistry '98 (Kashiwazaki City. Niigata: Japan Atomic Industrial Forum, 1998), p. 498.
256. B. Sala, S. Chevalier, A. Gelpi, H. Takenouti, M. Keddam, "Electrochemical Study of the Corrosion Processes of the Secondary Side of Steam Generators," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 587.
257. F. Vaillant, A. Stutzmann, "Duplication in Laboratory of Deposits, Films, and IGASCC Damage Observed on Pulled Steam Generator Tubes." Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. P. Ford, G. Was, L. Nelson (Houston, TX: NACE, 2002).
258. R.N. Parkins, "Stress Corrosion Cracking of Low-Carbon Steels," Proc. Fundamental Aspects of Stress Corrosion Cracking, eds. R.W. Staehle, A.J. Forty, D. van Rooyen (Houston, TX: NACE, 1969). p. 361.
259. K. Yamanaka, K. Tokimasa, H. Miyuki, H. Nagano, "IGA Behavior and Mechanism in Nickel-Based Alloys," 1987 EPRI Workshop on Secondary-Side Intergranular Corrosion Mechanisms, NP-5971, ed. M.J. Partridge (Palo Alto, CA: EPRI, 1987), p. 2/2.
260. H. Kawamura, H. Hirano, "Intergranular Attack and Stress Corrosion Cracking Propagation Behavior of Inconel Alloy 600 in High-Temperature Water," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: TMS, 1993). p. 71.
261. A. McIlree, "Effects of Alumino-Silicate on the Stress Corrosion Cracking of Alloys 600 and 690," EPRI, Final Report 1002782 (Palo Alto, CA: EPRI. 2000).
262. R. Bandy, D, van Rooyen, "Mechanisms of Intergranular Failures in Alloy 600 in High-Temperature Environments," Int. Congress on Metallic Corrosion, ed. H.P. Godard (Ottawa, Canada: National Research Council, 1984). p. 202.
263. S. Suzuki, "IGA Resistance of TT Alloy 690 and Concentration Behavior of Broached Egg Crate Tube Support Configuration," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1992). p. 752.
264. N. Pessall, Corros. Sci. 20 (1980): p. 225.
265. J.B. Lumsden, P.J. Stocker, "Inhibition of IGA In Nickel-Based Alloys in Caustic Solutions," CORROSION/88, paper no. 252 (Houston, TX: NACE. 1988), p. 252/ 1.
266. H. Nagano, K. Yamanaka, T. Minami, M. Inoue, T. Yonezawa, K. Onimura, N. Sasaguri, T. Kusakabe, "Effect of Alloying Elements and Heat Treatment on the Corrosion Resistance of Alloy 690," Proc. Workshop on Thermally Treated Alloy 690 Tubes for Nuclear Steam Generators, NP-4665S SR, ed. C.E. Shoemaker (Palo Alto, CA: EPRI. 1986), p. 10/ 1.
267. K. Yamanaka, T. Yonezawa, "Carbon Solubility of Alloy 690," EPRI Alloy 690 Workshop, NP-6750 SD, ed. J.A. Gorman (Palo Alto, CA: EPRI, 1990). p. 3/2.
268. R.J. Jacko, "Corrosion Evaluation of Thermally Treated Alloy 600 Tubing in Primary and Faulted Secondary Water Environments," NP-6721 (Palo Alto, CA: EPRI, 1990).
269. F. Valliant, "Comparative Behavior of Alloys 600, 690, and 800 in Caustic Environments" Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995). p. 219.
270. F. Valliant, E.M. Pavageau, M. Bouchacourt, J.M. Boursier. P. Lemaire, "Modeling the Secondary Side of Tubings: A Help to the Maintenance Police of PWR Steam Generators," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 679.
271. F. Vaillant, D. Buisine, B. Prieux, J.C. Fournel, A. Gelpi, "Effects of Microstructure and Mechanical Properties of Alloys 600 and 690 on Secondary-Side SCC," Control of Corrosion on the Secondary Side of Steam Generators, eds. R.W. Staehle, J.A. Gorman, A.R. McIlree (Houston, TX: NACE, 1996), p. 321.
272. B. Prieux, F. Vaillant, F. Cattant, A. Stutzmann, P. Lemaire. "Secondary-Side Cracking at Saint-Laurent Unit B2: Investigations, Operating Chemistry, and Corrosion Tests," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1994), p. 383.
273. V.B. Rajan, J.K. Sung, G.S. Was, "Stress Corrosion Cracking of Controlled Purity Inconel 600 Type Alloys in High-Purity Water and Caustic Solutions," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. eds. G.J. Theus, J.R. Weeks (Warrendale, PA: TMS, 1988), p. 545.
274. L.D. Kramer, S.T. Michael, Mater. Perform. 14 (1975): p. 15.
275. G.P. Airey, Corrosion 41 (1985): p. 1.
276. G.J. Theus, "Stress Corrosion Cracking Tests of Alloy 600," Proc. Workshop U-Bend Tube Cracking in Steam Generators. WS-80-136, ed. C.E. Shoemaker (Palo Alto, CA: EPRI, 1981), p. 15/3.
277. R. Pathania, "Overview of Caustic IGA/IGSCC Studies and Mechanisms," 1987 EPRI Workshop on Secondary-Side Intergranular Corrosion Mechanisms, NP-5971, ed. M.J. Partridge (Palo Alto, CA: EPRI, 1987), p. 2/ 1.
278. G.J. Theus, "Summary of the Babcock and Wilcox Company's Stress Corrosion Cracking Tests of Alloy 600," EPRI Workshop on Cracking of Alloy 600 U-Bend Tubes in Steam Generators, WS-80-136, ed. C.E. Shoemaker (Palo Alto, CA: EPRI. 1981). p. 15-1.
279. I.L.W. Wilson, F.W. Pement, R.G. Aspden, R.T. Begley, Nucl. Technol. 31 (1975): p. 70.
280. K. Smith, A. Klein, P. Saint-Paul, J. Blanchet, "Inconel 690: A Material with Improved Corrosion Resistance for PWR Steam Generator Tubes," Proc. 2nd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1986), p. 319.
281. R.T. Begley, A.W. Klein, R.E. Gold, "Investigation of ID Stress Corrosion Cracking in Field and Laboratory Programs." Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in PWR Plants (Paris, France: French Nuclear Energy Society, 1985), p. 217.
282. R.W. Pritchard. "Connecticut Yankee Atomic Power Company Haddam Neck Plant 1995 Refueling Outage Steam Generator Tube Inspection Report," NRC Public Document Room Accession no. 9506160449 950524 PDR ADOCK 05000213, prepared May 19, 1995.
283. M.M. Hall, Jr., D.M. Symons, "Hydrogen-Assisted Creep Fracture Model for Low-Potential Stress Corrosion Cracking of Ni-Cr-Fe Alloys," Chemistry and Electrochemistry of Corrosion and Stress Corrosion Cracking: A Symposium Honoring the Contributions of R.W. Staehle, R.H. Jones, ed. (Warrendale, PA: TMS, 2001). p. 447.
284. M.M. Hall, Jr., "Thermally Activated Dislocation Creep Model for Primary Water Stress Corrosion Cracking of NiCrFe Alloys," Proc. Int. Symp. on Plant Aging and Life Prediction of Corrodible Structures, eds. T. Shoji. T. Shibata (Houston, TX: NACE, 1997), p. 107.
285. T. Magnin, J.-M. Boursier, D. Noel, R. Rios, F. Vaillant, "Corrosion Deformation Interaction during Stress Corrosion Cracking of Alloy 600 in Primary Water." Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: TMS, 1993), p. 669.
286. P.M. Scott, M. Le Calvar, "Some Possible Mechanisms of Intergranular Stress Corrosion Cracking of Alloy 600 in PWR Primary Water," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: TMS, 1993), p. 657.
287. P.M. Scott, M. Le Calvar, "Some Possible Mechanisms of Intergranular Stress Corrosion Cracking of Alloy 600 in PWR Primary Water," Proc. Specialist Meeting on Environmental Degradation of Alloy 600. TR- 104898, eds. R.G. Ballinger, A.R. McIlree, J.P.N. Paine (Palo Alto, CA: EPRI, 1994), p. 17/ 1.
288. A.F. Gourgues, P.M. Scott, E. Andrieu, "A Study of the Mechanism of Primary Water Stress Corrosion Cracking of Alloy 600," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE. 1995), p. 829.
289. T.S. Gendron, P.M. Scott, S.M. Bruemmer, L.E. Thomas, "Internal Oxidation as a Mechanism for Steam Generator Tube Degradation," 3rd Int. Steam Generator and Heat Exchanger Conf. (Toronto, Canada: Canadian Nuclear Society, 1998), p. 389.
290. R.W. Staehle, Z. Fang, "Comments on a Proposed Mechanism of Internal Oxidation for Alloy 600 as Applied to Low-Potential SCC," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 69.
291. P.L. Andresen, T.M. Angeliu, "Evaluation of the Role of Hydrogen in SCC in Hot Water," CORROSION/97, paper no. 195 (Houston, TX: NACE. 1997), p. 195/ 1.
292. T.M. Angeliu, P.L. Andresen, M.L. Pollick, "Repassivation and Crack Propagation of Alloy 600 in 288°C Water," CORROSION/ 96, paper no. 86 (Houston, TX: NACE, 1996), p. 86/ 1.
293. P.G. Shewmon, "A Mechanism for Hydrogen-Induced IGSCC in Inconel 600," Advances in Fracture Research, eds. K. Salama, K. Ravi-Chandar, D. Taplin, P. Rama Rao (New York, NY: Pergamon Press, 1998), p. 1,555.
294. Y. Shen, P.G. Shewmon, Corrosion 47 (1991): p. 712.
295. Y. Shen, P.G. Shewmon, Met. Trans. 22A (1991): p. 1,857.
296. C.H. Shen, P.G. Shewmon, Met. Trans. 21A (1990): p. 1,261.
297. H. Takamatsu, K. Matsueda, "IGA/IGSCC Propagation Behaviors of Alloy 600," Proc. 4th Ind. Symp. on Environmental Degradation of
298. R.J. Jacko, "Effect of Lithium Hydroxide on Primary Water Stress Corrosion Cracking of Alloy 600 Tubing." NP-7396 M (Palo Alto, CA: EPRI, 1991).
299. 2O IGSCC, NP-5987-SP, eds. G. Economy, R.J. Jacko, J.A. Begley, F.W. Pement (Palo Alto, CA: EPRI, 1987).
300. P.M. Scott, P. Combrade, "On the Mechanisms of Secondary-Side PWR Steam Generator Tube Cracking," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 65.
301. D.H. Lee, M.S. Choi, U.C. Kim, "The Effect of Hydrogen on the Stress Corrosion Cracking of Alloy 600 in Simulated PWR Primary Water at 330°C," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. P. Ford, G. Was, L. Nelson (Houston, TX: NACE, 2002).
302. N. Totsuka, M. Kamaya, N. Nakajima, H. Mitsuda, S. Sakai, "A New Evaluation Method for Short Crack Growth and Influence of Dissolved Hydrogen on PWSCC of Alloy 600," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. P. Ford, G. Was, L. Nelson (Houston, TX: NACE, 2002).
303. T. Tsuruta, S. Okamoto, T. Kitera, Y. Katsura, H. Takamatsu, K. Matsueda, T. Matsunaga, "Effect of Impurity Ions on IGSCC Behavior of Mill-Annealed Alloy 600 Steam Generator Tubing under 400°C Steam Tests," 2nd Int. Steam Generator and Heat. Exchange Conf., ed. D. E. Anderson (Toronto, Canada: Canadian Nuclear Society, 1994), p. 6/34.
304. ton, S.A. Attanasio, G.A. Young, "Primary Water SCC Understanding and Characterization through Fundamental Testing in the Vicinity of the Nickel/Nickel Oxide Phase Transition," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. eds. P. Ford, G. Was, L. Nelson (Houston, TX: NACE, 2002).
305. T. Yonezawa, K. Onimura, "Effect of Chemical Compositions and Microstructure on the Stress Corrosion Cracking Resistance of Nickel-Based Alloys in High-Temperature Water." Int. Conf. on Evaluation of Materials Performance in Severe Environments, EVALMAT '89 (Tokyo, Japan: The Iron and Steel Institute of Japan, 1989). p. 235.
306. H. Coriou, L. Grall, M. Pelras, "Studies of the Corrosion Resistance of Chromium Nickel Iron Austenitic Alloys with a View to Their Application in the Nuclear Field," 3rd Int. Congress in Metal Corrosion, ed. M. Kolotyrkin (Amsterdam, The Netherlands: Swets and Zeitlinger. 1969), p. 303.
307. J.K. Sung, G.S. Was, Corrosion 47 (1991): p. 824.
308. G. Sui, G.B. Heys, J. Congleton, " Stress Corrosion Cracking of Alloy 600 and Alloy 690 In Hydrogen/Steam and PWR Primary Side Water," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997). p. 274.
309. P.M. Scott, Corrosion 56 (2000): p. 771.
310. F. Cattant, D. Garriga-Majo, F. de Keroulas, P. Todeschini, J.C. Van Duysen, "Effectiveness of 700°C Thermal Treatment on Primary Water Stress Corrosion Sensitivity of Alloy 600 Steam Generator Tubes: Laboratory Tests and In-Field Experience," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1992), p. 901.
311. G.P. Airey, "The Stress Corrosion Cracking [SCC) Performance of Inconel Alloy 600 in Pure and Primary Water Environments." Proc. Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE. 1984), p. 462.
312. W.H. Cullen, "Review of IGA. IGSCC, and Wastage of Alloys 600 and 690 in High-Temperature Acidified Solutions," Control of Corrosion on the Secondary Side of Steam Generators. R.W. Staehle, J.A. Gorman, A.R. McIlree, eds. (Houston, TX: NACE, 1996), p. 273.
313. T.M. Angeliu, G.S. Was, "Grain Boundary Chemistry and Precipitation in Controlled Purity Alloy 690." Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, D. Cubicciotti, ed. (Houston, TX: NACE, 1990), p. 5/64.
314. P. Saint-Paul, G. Zacharie. "Corrosion under Pressure of Alloy 600 in Water." EDF/DER/EMA no. D 729A (Paris, France: Electricite de France, 1990).
315. D. Garriga-Majo, J.M. Gras, Y. Rouillon, F. Vaillant, J.C. Van Duysen, G. Zacharie, "Prediction of the Stress Corrosion Cracking Resistance of Alloy 600 in Pure/Primary Water," Life Prediction of Corrodible Structures, ed. R.N. Parkins (Houston, TX: NACE, 1994), p. 1104.
316. G. P. Airey, "Optimization of Metallurgical Variables to Improve Corrosion Resistance on Inconel Alloy 600," NP-3051 (Palo Alto, CA: EPRI, 1983).
317. M.O. Speidel, R. Magdowski, "Stress Corrosion Crack Growth of Cold-Worked Nickel-Based Alloy 600," Int. Cord. on Corrosion-Deformation Interactions, CDI '92 (Paris, France: Electricite de France, 1992). p. 107.
318. M.O. Speidel, A. Atrens, "Corrosion in Power Generating Equipment," Proc. 8th Int. Brown Boveri Symp. on Corrosion in Power Generating (New York, NY: Plenum Press, 1984), p. 88.
319. G.V. Rao, "Methodologies to Assess PWSC Susceptibility of Primary Component Alloy 600 Locations in Pressurized Water Reactors," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: TMS, 1993), p. 871.
320. Ph. Berge, D. Buisine, A. Gelpi, "Surface Preparation and Stress Corrosion Cracking Models." Proc. 13th Int. Corrosion Conf. (Clayton, Australia: Australasian Corrosion Association, 1996). p. 244/1
321. J.A. Gorman, R.W. Staehle, K.D. Stavropoulos. "Statistical Analysis of Steam Generator Tube Degradation." NP-7493 (Palo Alto. CA: EPRI, 1991).
322. T.B. Cassagne, P. Combrade, M.A. Foucault, A. Gelpi. "The Influence of Mechanical and Environmental Parameters on the Crack Growth Behavior of Alloy 600 in PWR Primary Water," 12th Scandinavian Corrosion Congress and Eurocorr'92, ed. P.J. Tunturi (Helsinki, Finland: Corrosion Society of Finland, 1992), p. 55.
323. P.M. Scott, "Prediction of Alloy 600 Component Failures in PWR Systems," Proc. Corrosion '96: Part 1: Life Prediction of Structures Subject to Environmental Degradation" (Houston, TX: NACE, 1996), p. 135.
324. H.T. Krasodomski, J.S. Fish, N. Lewis, W.J. Yang, "Analysis of PWSCC Initiation and Crack Growth in Laboratory Specimens and Components as a Function of Material Condition," Proc. 1997 Workshop on PWSCC of Alloy 600 In PWRs, TR- 109138, ed. S. Hunt (Palo Alto, CA: EPRI, 1997). p. E13/ 1.
325. J. Jansson, U. Morin, "Assessment of Crack Growth Rates in Austenitic Stainless Steels in Operating BWRs," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 667.
326. A.R. McIlree, T. Olberg, J. Nestell, Steam Generator Owners Group. "Primary Side Stress Corrosion Cracking: Chapter Seven," Steam Generator Reference Book (Palo Alto, CA: EPRI, 1985). p. 7/1.
327. H.J. Schenk, Mater. Perform. 3 (1976): p. 25.
328. Workshop Proc. U-Bend Tube Cracking in Steam Generators. WS-80-136, ed. C.C. Shoemaker (Palo Alto, CA: EPRI, 1981).
329. "Stress Relief to Prevent Stress Corrosion in the Transition Region of Expanded Alloy 600 Steam Generator Tubing." EPRI-Steam Generators Owners Group Research Project S192-3, Final Report. NP-3055 (Palo Alto, CA: EPRI, 1983).
330. H. Domain, R.H. Emanuelson, L. Katz, L.W. Sarver, G.J. Theus, Corrosion 33 (1977): p. 26.
331. R.S. Pathania, D. Lim, "Stress Corrosion Cracking of Expanded Tube-to-Tubesheet Joints in Steam Generators," Proc. Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE, 1984), p. 254.
332. G.L. Webb, "Environmental Degradation of Alloy 600 and Welded Filler Metal EN 82 in an Elevated Temperature Aqueous Environment." Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: TMS, 1993). p. 687.
333. R. Bandy, D. van Rooyen, "Tests with Inconel 600 to Obtain Quantitative Stress Corrosion Cracking Data for Evaluating Service Performance," BNL-NUREG-31814 (Washington, DC: U.S. Nuclear Regulatory Commission, 1983).
334. D. Alter, Y. Robin, M. Pichon, A. Teissier, B. Thomeret, "Stress Corrosion Cracking of Pressurizer Instrumentation Nozzles in the French 1300 Mwe Units," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1992). p. 661.
335. R. Boudot, F. Cattant, C. Pichon, Y. Rouillon, A. Teissier, P. Vidal, A. Gelpi, M. Gregoire, C. Gimond, T. Tsuk, "Stress Corrosion Cracking of Pressurizer Nozzles in French 1300 Mwe Units." Proc. Int. Symp. Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1994), p. 155.
336. R.J. Jacko, L.E. Willertz. "The Corrosion Fatigue Performance of Ni-Cr-Fe Alloy 600 under Typical PWR Steam Generator Conditions." Proc. Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (Houston, TX: NACE. 1984). p. 775.
337. G. Ogundele, O. Lepik, "Fatigue Cracking of Alloy 600 in Simulated Steam Generator Crevice Environment," 3rd Int. Steam Generator and Heat Exchanger Conf. (Toronto, Canada: Canadian Nuclear Society, 1998). p. 308.
338. Z. Fang, R.W. Staehle, Corrosion 55 (1999): p. 355.
339. D. Choi, G.S. Was. Corrosion 46 (1990): p. 100.
340. J.F. Newman, "Stress Corrosion of Alloys 600 and 690 in Acidic Sulfate Solutions at Elevated Temperatures," NP-3043 (Palo Alto CA: EPRI, 1983).
341. O. deBouvier, F. Vaillant, M. Bouchacourt, P. Lemaire, "Effect of Copper Species on IGA/SCC of Alloy 600 In Neutral Sulfate Environments." Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. P. Ford, G. Was, L. Nelson (Houston. TX: NACE, 2002).
342. D. Choi, G.S. Was, Corrosion 46 (1990): p. 100.
343. N. Totsuka, Z. Szklarska-Smialowska, Corrosion 43 (1987): p. 734.
344. L.G. Ljungberg, D. Cubicciotti, M. Trolle, "Crack Propagation in Alloys 600 and 182 in Simulated BWR Environments," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1992). p. 226.
345. P.L. Andresen, "Effects of Testing Characteristics on Observed SCC Behavior in BWRs." CORROSION/98, paper no. 137 (Houston, TX: NACE. 1998), p. 137/1.
346. C. R. Frye, "Laboratory Evaluation of Steam Generator Tubes 120/12. 79/9, and 59/95 from St. Lucie Unit 1," NP-5397-LD (Palo Alto. CA: EPRI, 1987).
347. F. Cattant, "Chemical Analysis of OD Deposits Removed from SG Tubes," Proc. 1993 EPRI Workshop on Secondary-Side IGA/SCC. TR 107883, eds. M.J. Partridge, J.E. Broussard (Palo Alto, CA: EPRI, 1993), p. A/2.
348. A. Rocher, F. Nordmann, F. Cattant, F. de Keroulas, "Investigation into Lead Limitation in Steam Generators," Conf. Proc. Steam Generator and Heat Exchanger Conf.. vol. 2 (Toronto, Canada: Canadian Nuclear Society, 1994). p. 6/47.
349. P.J. King, F. Gonzalez, J. Brown, "Stress Corrosion Cracking Experience in Steam Generators at Bruce NGS." Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold. E.P. Simonen (Warrendale, PA: TMS. 1993), p. 233.
350. C. Laire, J. Stubbe, E. Pierson, "Doel 4: Secondary-Side Corrosion Mechanisms and Effects of Phosphate Injections," IAEA Specialists' Meeting on Steam Generator Problems and Replacement (Vienna, Austria, International Atomic Energy Agency, 1994), p. 51.
351. S.S. Hwang, H.P. Kim, J.S. Kim, Corrosion 59, 9 (2003): p. 821.
352. S.M. Bruemmer, L.E. Thomas, "Insights into Environmental Degradation Mechanisms from High-Resolution Characterization of Crack Tips," Chemistry and Electrochemistry of Corrosion and Stress Corrosion Cracking: A Symposium Honoring the Contributions of R.W. Staehle, ed. R.H. Jones (Warrendale, PA: TMS, 2001). p. 123.
353. A.K. Agrawal, J.P.N. Paine. "Lead Cracking of Alloy 600-A Review," Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. D. Cubicciotti (Houston, TX: NACE, 1990). p. 7-1.
354. J.C. Sawyer, Trans. Met. Soc. AIME 221 (1961): p. 63.
355. M. Helie, I. Lambert, G. Santarini, "Some Considerations about the Possible Mechanisms of Lead-Assisted Stress Corrosion Cracking of Steam Generator Tubing," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995). p. 247.
356. R. Kilian, "Influence of Lead on the SCC Behavior of SG Tubing Materials," IAEA Specialists Meeting on Steam Generator Problems and Replacement (Madrid. Spain: International Atomic Energy Agency, 1993). p. 137.
357. T. Sakai, S. Okabayashi, K. Aoki, K. Matsumoto, Y. Kishi, "A Study of Oxide Thin Film of Alloy 600 in High-Temperature Water Containing Lead," CORROSION/90, paper no. 520 (Houston, TX: NACE, 1990), p. 520/1.
358. H. Takamatsu, B.P. Miglin, P.A. Sherburne, K. Aoki, "Study on Lead-Induced Stress Corrosion Cracking of Steam Generator Tubing under AVT Water Chemistry Conditions." Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society. 1997). p. 216.
359. W.A. Byers, J. Barkich, M.W. Rootham, F. Hundley, "Control of Lead-Assisted Stress Corrosion Cracking of Alloy 600 Tubing in Steam Generator Free-Span Locations," Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1997), p. 224.
360. T. Sakai, T. Senjuh, K. Aoki, T. Shigemitsu, Y. Kishi, "Study on Corrosion Resistance of Alloy 600 and 690 in High-Temperature Water Containing Lead, CORROSION/92. paper no. 83 (Houston. TX: NACE, 1992). p. 83/1.
361. 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," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered In Pressurized Water Reactors (Paris, France: French Nuclear Energy Society, 1998), p. 403.
362. A. Seidell, Solubilities of Inorganic and Organic Compounds, 2nd ed. (New York. NY: Van Nostrand Co., 1919).
363. H. Stephen, T. Stephen, Solubilities of Inorganic and Organic Compounds, vol. 1 (New York, NY: Pergamon Press, 1979).
364. K.K. Chung, J.K. Lim, S. Moriya, Y. Watanabe, T. Shoji, "Lead-Induced Stress Corrosion Cracking of Alloy 690 in High-Temperature Water." Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R, Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995). p. 233.
365. G.P. Airey, Corrosion 36 (1979): p. 129.
366. J.M. Sarver, "IGSCC of Nickel Alloys in Lead-Contaminated High-Purity Water, "EPRI Workshop on Intergranular Corrosion and Primary Water Stress Corrosion Cracking Mechanisms. NP-5971 (Palo Alto. CA: EPRI, 1987), p. C11/1.
367. T. Sakai, T. Senjuh, K. Aoki, T. Shigemitsu, Y. Kishi, "Lead-Induced Stress Corrosion Cracking of Alloy 600 and 690 in High-Temperature Water." Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (La Grange Park, IL: American Nuclear Society, 1992), p. 764.
368. S.S. Hwang, Y.S. Park, I.S. Jeong, S.Y. Hong, U.C. Kim, J. Corros. Sci. Soc. Korea 25 (1996): p. 327.
369. M.L. Castano-Marin, D. Gomez-Briceno, F. Hernandez-Arroyo, "Influence of Lead Contamination on the Stress Corrosion Resistance of Nickel Alloys," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: TMS, 1993), p. 189.
370. F. Valliant, D. Buisine, B. Prieux, D. Gomez-Briceno, L. Castano. "Influence of Lead on the Secondary-Side Cracking of Alloys 600, 690, and 800," Eurocorr '96, Session IX: Nuclear Corrosion and Protection, Extended Abstracts (Nice, France: Centre Francais de L'Anticorrosion Societe de Chimie Industrielle. 1996). p. 13-1.
371. M.D. Wright, M. Mirzai, 'Lead-Induced SCC Propagation Rates in Alloy 600," Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999), p. 657.
372. M.D. Wright, "Establishing Thresholds for Lead-Induced Cracking of Steam Generator Tube Alloys." Water Chemistry of Nuclear Reactor Systems, 7 (London, U.K.: British Nuclear Energy Society, 1996). p. 435.
373. Y.C. Lu, M.D. Wright, R.D. Cleland, "Effect of Lead and Silicon on Localized Corrosion of Alloy 800 in Steam Generator Crevice Environments," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. P. Ford, G. Was, L. Nelson (Houston, TX: NACE, 2002).
374. F. Vaillant, D. Buisine, B. Prieux, D. Gomez Briceno, L. Castano, "Influence of Lead on the Secondary-Side Cracking of Alloys 600, 690, and 800," Eurocorr '96. Session IX: Nuclear Corrosion and Protection, Extended Abstracts (Nice, France: Centre Francais de L'Anticorrosion Societe de Chimie Industrielle, 1996). p. 13-1.
375. A. Rocher, F. Cattant, D. Buisine, B. Prieux, M. Helie, "Effect of Lead on the OD Degradation of Steam Generator Tubes," Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors (Paris, France: French Nuclear Energy Society. 1994), p. 537.
376. D.G. Slear, R.L. Long, J.D. Jones, F.S. Giacobbe, Plant Oper. Prog. 2 (1983): p. 173.
377. T. Sakai, K. Aoki, T. Shigemitsu, Y. Kishi, Zairyo-to-Kankyo 40 (1991): p. 736.
378. M. Helie, "Lead-Assisted Stress Corrosion Cracking of Alloys 600, 690, and 800," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. R.E. Gold, E.P. Simonen (Warrendale, PA: TMS, 1993). p. 179.
379. D.G. Briceno, L. Castano, "Inconel 690TT and Incoloy 800 in S, Cu, and Pb Environments." EPRI Workshop on Steam Generator Secondary-Side ICA/SCC (Palo Alto, CA: EPRI, 1991).
380. R.C. Newman, R. Roberge, R. Bandy, Corrosion 39 (1983): p. 386.
381. R. Bandy, D. Van Rooyen, Corrosion 40 (1984): p. 281.
382. M.-C. Tsai, W.-T. Tsai, J.-T. Lee, Corros. Sci. 34 (1993): p. 741.
383. W.-T. Tsai, Z.-H. Lee, J.-T. Lee, Corrosion 45 (1989): p. 883.
384. J. Daret, J. P.N. Paine, M.J. Partridge, "Model Boiler Testing to Evaluate Inhibitors for Caustic-Induced Stress Corrosion Cracking of Alloy 600 Tubes," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995), p. 177.
385. J. Daret, "Intergranular Corrosion of Alloy 600 Tubing in PWR's a Steam Generators at the Tube Support Plate Elevation: A Model Boiler Study." Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. D. Cubicciotti (Houston, TX: NACE, 1990). p. 7/45.
386. T. Cassagne, J. Daret, "PWSCC Crack Propagation of Alloy 600 in Vessel Head Penetration." Proc. 1997 Workshop on PWSCC of Alloy 600 in PWRs. TR-109138, ed. S. Hunt (Palo Alto, CA: EPRI. 1997), p. E8-1.
387. J. Daret, D. Feron, R. Besnard, C. Gondard, "Model Boiler Test Results with Inhibitors,-Inhibition of IGA/SCC on Alloy 600 Surfaces Exposed to PWR Secondary Water, RPS 407-53 (Palo Alto. CA: EPRI, 1993). p. C13-1.
388. J. Daret, T. Cassagne, "Testing Secondary-Side SCC Causes and Remedies under Representative Thermo-Hydraulic Conditions: A Necessity," Eurocorr '96, Session IX: Nuclear Corrosion and Protection. Extended Abstracts (Nice, France: Centre Francais de L'Anticorrosion Societe de Chimie Industrielle, 1996), p. 9/ 1.
389. S. Lee, R.W. Staehle, Mater. Corros. 48 (1997): p. 86.
390. S. Lee, R.W. Staehle, Corrosion 53 (1997): p. 33.
391. S. Lee, R.W. Staehle, J. Electrochem. Soc. 142 (1995): p. 2.189.
392. S. Lee, R.W. Staehle, Corrosion 52 (1996): p. 843.
393. S. Lee, R.W. Staehle, Mater. Trans. 12 (1996): p. 1,786.
394. F. Vaillant, A. Stutzmann, "Duplication in Laboratory of Deposits, Films, and IGASCC Damage Observed on Pulled Steam Generator Tubes," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. P. Ford, G. Was, L. Nelson (Houston. TX: NACE, 2002).
395. E.A. Moelwyn-Hughes, Physical Chemistry. 2nd rev. ed. (New York, NY: Pergamon Press, 1961). p. 921.
396. M.J. Blackburn, J.A. Feeney, T.R. Beck, "Stress Corrosion Cracking of Titanium Alloys," Advances in Corrosion Science and Technology, vol. 3, eds. M.G. Fontana, R.W. Staehle (New York, NY: Plenum Press, 1973), p. 67.
397. E. Pierson, J. Stubbe, W.H. Cullen, S.M. Kazanjian, J.P.N. Paine, "How to Simulate Acid Corrosion of Alloy 600 Steam Generator Tubes," Proc. 7th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. eds. G. Airey, P. Andresen, J. Brown, S. Bruemmer, R. Cowan, P. Doherty, P. Ford, F. Garner, F. Garzarolli, G. Gordon, J. Hall, N. Iyer, C. Jansson, F. de Keroulas, H. Levin, G. Lucas, A. McIlree, B. Miglin, P. Millet, W. Mills, R. Pathania, J. Perrin, S. Sawochka, P. Scott, E. Simonen, T. Shoji, H. Takamatsu, R. Tapping, G. Theus, C. Thompson, G. Was, J. Weeks, T. Yonezawa (Houston, TX: NACE, 1995), p. 303.
398. Z. Xia, W. Lai, Z. Szklarska-Smialowska, Corrosion 47 (1991): p. 173.
399. W.J. Mills, C.M. Brown, "Fracture Toughness of Alloy 600 and EN82H Weld in Air and Water." Bechtel Bettis Report, B-T-3264 (West Mifflin, PA: Bechtel Bettis, 1999).
400. W.J. Mills, C.M. Brown, M.G. Burke, "Fracture Behavior of Alloy 600, Alloy 690, EN82H Welds, and EN52 Welds In Water," Bechtel Bettis Report. B-T-3303 [West Mifflin, PA: Bechtel Bettis, 1999).
401. W.J. Mills, C.M. Brown, "Fracture Behavior of Nickel-Based Alloys in Water." Proc. 9th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. S.M. Bruemmer, F.P. Ford, G.S. Was (Warrendale, PA: TMS, 1999). p. 167.
402. W.J. Mills, C.M. Brown, M.G. Burke, "Fracture Behavior of Alloy 600. Alloy 690. EN82H Welds, and EN52 Welds in Water." EPRI 2000 Workshop on PWSCC of Alloy 600 in PWRs. held February 14-16 (Palo Alto. CA: EPRI, 2000).