Effects of PWR primary water chemistry and deaerated water on SCC

Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Volumn , Issue , 2005, Pages 989-1008

  Andresen, Peter L ^a   Emigh, Paul W ^a   Morra, Martin M ^a   Hickling, John ^b  

^a GE GLOBAL RESEARCH   (United States)

^b ELECTRIC POWER RESEARCH INSTITUTE   (United States)

Author keywords

Boron and lithium effects; Corrosion potential; Crack growth rates; High temperature water; Ni alloys; PH; PWR; Stainless steel; Stress corrosion cracking; Stress intensity factor; Water chemistry

Indexed keywords

BORON AND LITHIUM EFFECTS; CORROSION POTENTIAL; CRACK GROWTH RATES; DEAERATED WATER; WATER CHEMISTRY;

BORON; CRACK PROPAGATION; HIGH TEMPERATURE EFFECTS; LITHIUM; NICKEL ALLOYS; PH EFFECTS; STAINLESS STEEL; STRESS CORROSION CRACKING; STRESS INTENSITY FACTORS; WATER;

PRESSURIZED WATER REACTORS;

EID: 33745213546     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (39)

1. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE / ANS / TMS, 1983 - 2001.
2. F.P. Ford and P.L. Andresen, "Corrosion in Nuclear Systems: Environmentally Assisted Cracking in Light Water Reactors", in Corrosion Mechanisms, Ed. P. Marcus and J. Ouder, Marcel Dekker, p.501-546, 1994.
3. P.L. Andresen and F.P. Ford, "Life Prediction by Mechanistic Modelling and System Monitoring of Environmental Cracking of Fe and Ni Alloys in Aqueous Systems", Materials Science and Engineering, A103, pp.167-183, 1988.
4. F.P. Ford, D.F. Taylor, P.L. Andresen and R.G. Ballinger, "Corrosion Assisted Cracking of Stainless and Low Alloy Steels in LWR Environments", EPRI Contract RP2006-6, Report NP5064M, 1987.
5. P.L. Andresen, "Perspective and Direction of Stress Corrosion Cracking in Hot Water", Proc. Tenth Int. Symp. on Env. Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, 2001.
6. P.L. Andresen, "Conceptual Similarities and Common Predictive Approaches for SCC in High Temperature Water Systems", Paper 96258, Corrosion/96, NACE, 1996.
7. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, pp. 1-83 to 1-121, 1990.
8. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, p.579-596, 1995.
9. P.L. Andresen and F.P. Ford, "Response to 'On the Modeling of Stress Corrosion Cracking of Iron and Nickel Base Alloys in High Temperature Aqueous Environments' ", Corrosion Science Vol 38, p.1011-1016, 1996.
10. Y.J. Kim, L.W. Niedrach, M.E. Indig and P.L. Andresen, "Applications of Noble Metals in Coatings and Alloys for Light Water Reactors", J. of Metals, Vol. 44, No. 2, p. 14-18, April 1992.
11. th Int. Symp. on Env. Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, p.563-578, 1995.
12. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, p.735-746, 1995.
13. P.L. Andresen, P.W. Emigh, M.M. Morra and R.M. Horn, "Effects of Yield Strength, Corrosion Potential, Stress Intensity Factor, Silicon and Grain Boundary Character on the SCC of Stainless Steels", Proc. of 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, 2003.
14. P.L. Andresen, T.M. Angeliu, L.M. Young, W.R. Catlin, and R.M. Horn, "Mechanisms and Kinetics of SCC in Stainless Steels", Proc. Tenth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, 2001.
15. P.L. Andresen, T.M. Angeliu, W.R. Catlin, L.M. Young and R.M. Horn, "Effect of Deformation on SCC of Unsensitized Stainless Steel", Corrosion/2000, Paper 00203, NACE, 2000.
16. P.L. Andresen, T.M. Angeliu and L.M. Young, "Effect of Martensite and Hydrogen on SCC of Stainless Steels", Paper #01228, Corrosion/01, NACE, 2001.
17. P.L. Andresen, "Similarity of Cold Work and Radiation Hardening in Enhancing Yield Strength and SCC Growth of Stainless Steel in Hot Water", Corrosion/02, Paper 02509, NACE, 2002.
18. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, 2003.
19. P.L. Andresen and C.L. Briant, "Environmentally Assisted Cracking of Types 304L/316L/316NG Stainless Steel in 288°C Water," Corrosion, Vol. 45, pp. 448-463, 1989.
20. P.L. Andresen and C.L. Briant, "Role of S, P and N Segregation on Intergranular Environmental Cracking of Stainless Steels in High Temperature Water," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME, pp. 371-382, 1988.
21. P.L. Andresen, "Environmentally Assisted Growth Rate Response of Nonsensitized AISI 316 Grade Stainless Steels in High Temperature Water," Corrosion 44, 7, p. 450, 1988.
22. P.L. Andresen, "The Effects of Aqueous Impurities on Intergranular Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel," Final Report NP3384 Contract T115-3, EPRI, 1983.
23. See also, "Innovations in Experimental Techniques for Testing in High Temperature Aqueous Environments," Report No. 81CRD088, GE CRD, Schenectady, New York, 1981.
24. L.W. Niedrach, "A New Membrane Type pH Sensor for Use in High Temperature High Pressure Water", J. Electrochem. Soc. 127, p. 2122, 1980.
25. P.L. Andresen, L.M. Young, P.W. Emigh and R.M. Horn, "Stress Corrosion Crack Growth Rate Behavior of Ni Alloys 182 and 600 in High Temperature Water", Corrosion/02, Paper 02510, NACE, 2002.
26. P.L. Andresen, "Fracture Mechanics Data and Modeling of Environmental Cracking of Nickel-Base Alloys in High Temperature Water", Corrosion 47, Dec.1991, p. 917-938.
27. P.L. Andresen, unpublished data, GE Global Research, Schenectady, NY, 2003.
28. P.L. Andresen, P.W. Emigh, M.M. Morra, "SCC of High Strength Ni-base Alloys in High Temperature Water", Paper #04675, Corrosion/04, NACE, 2004.
29. Y.J. Kim and P.L. Andresen, "Data Quality, Issues and Guidelines for ECP Measurements in High Temperature Water", Corrosion/2001, Paper 01137, NACE, 2001.
30. Y.J. Kim, "Effect of Variation in BWR Water Chemistry on Type 304 SS ECP", Corrosion Vol. 58, p. 208-215, March 2002.
31. D.S. Morton and M. Hansen, "The Effect of pH on Nickel Alloy SCC and Corrosion Performance," Paper 03675, Corrosion/03, NACE, 2003.
32. th Int. Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, 2003.
33. S.A. Attanasio and D.S. Morton, "Measurement of the Ni/NiO Transition in Ni-Cr-Fe Alloys and Updated Data and Correlation to Quantify the Effect of Aqueous Hydrogen on Primary Water SCC", Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, 2003.
34. S.A. Attanasio, D.S. Morton, M.A. Ando, N.F. Panayotou and C.D. Thompson, "Measurement of the Ni / NiO Phase Transition in High Temperature Hydrogenated Water Using the Contact Electrical Resistance (CER) Technique", Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, 2001.
35. D.S. Morton, S.A. Attanasio and G.A. Young, "Primary Water SCC Understanding and Characterization Through Fundamental Understanding in the Vicinity of the Ni / NiO Phase Transition", Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, 2001.
36. S. Attanasio, J. Mullen, J. Wuthrich, W. Wilkening, D. Morton, "SCC Growth Rates of Alloy 182 and 82 Welds", NRC Conference on PWR Vessel Penetration Inspection, Cracking and Repair, Gaithersburg, MD, September 2003.
37. T.M. Angeliu, P.L. Andresen, and M.L. Pollick, "Repassivation and Crack Propagation of Alloy 600 in 288C Water", Corrosion 53, p.114, 1997.
38. D.S. Morton, S.A. Attanasio, J.S. Fish, and M.K. Schurman, "Influence of Dissolved Hydrogen on Nickel Alloy SCC in High Temperature Water", Corrosion/99, Paper 99447, NACE, 1999.
39. C.D. Thompson, D.M. Carey, and N.L. Perazzo, "Effects of Hydrogen on Electropotential Monitoring of Stress Corrosion Crack Growth", Eighth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, p. 366, 1997.