Effects of PWR primary water chemistry on PWSCC of Ni alloys

Canadian Nuclear Society - 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007

Volumn 2, Issue , 2007, Pages 1393-1413

  Andresen, Peter L ^a   Hickling, John ^b   Ahluwalia, Kawaljit S ^c   Wilson, John A ^d  

^a GE GLOBAL RESEARCH   (United States)

^b CMC   (Germany)

^c ELECTRIC POWER RESEARCH INSTITUTE   (United States)

^d Exelon Corporation   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ALLOY 600; BORON CONCENTRATIONS; DISSOLVED HYDROGEN; INTERNATIONAL CONFERENCES; NUCLEAR POWER SYSTEMS; NUCLEAR SOCIETY; PRIMARY WATER; WELD METALS;

ALLOYS; BORON; BORON COMPOUNDS; CATALYST ACTIVITY; CHEMISTRY; DEGRADATION; DISSOLUTION; ELECTRIC POWER SYSTEMS; ELECTRIC POWER TRANSMISSION NETWORKS; HYDROGEN; HYDROLOGY; LITHIUM; METALLIC COMPOUNDS; METALS; NICKEL; NONMETALS; NUCLEAR ENERGY; POWER TRANSMISSION; PRESSURIZED WATER REACTORS; SULFATE MINERALS; WELDED STEEL STRUCTURES; ZINC;

SMALL NUCLEAR REACTORS;

EID: 51849121100     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (42)

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. th 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 SCC of Iron and Nickel Base Alloys in High Temperature Aqueous Environments'", Corrosion Science Vol 38, p.1011-1016, 1996.
10. st Int. Conf. on Environmental Degradation of Materials in Nuclear Power System Water Reactors, NACE, 1983,p.893.
11. M.E. Indig, G.M. Gordon, R.B. Davis, and J.E. Webber, "Evaluation of In-Reactor Intergranular Stress Corrosion Cracking via Electrochemical Measurements", Proc. 2" Int. Conf. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, NACE, 1985, p.411.
12. R.L. Cowan and E. Kiss, "Optimizing BWR Water Chemistry", Proc. 6th. Int. Conf. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, TMS, 1993, p. 889.
13. 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. 1418, April 1992.
14. th Int. Symp. on Env. Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, p.563-578, 1995.
15. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems, NACE, p.735-746, 1995.
16. P.L. Andresen and Thomas P. Diaz, "Effects of Zinc Additions on the Crack Growth Rate of Sensitized Stainless Steel and Alloys 600 and 182 in 288C Water", Bournemouth Conference, BNES, England, October 1993.
17. P.L. Andresen and Thomas P. Diaz, "Effects of Zinc Addition on Crack Growth Rates in High Temperature Water", Paper #93184, Corrosion/93, NACE, Houston, 1993.
18. P.L. Andresen and T.M. Angeliu, "Effects of Zinc Additions on the Stress Corrosion Crack Growth Rate of Sensitized Stainless Steel, Alloy 600, and Alloy 182 Weld Metal in 288C Water", Corrosion/95, Paper #95409, T-2A Symposium, NACE, 1995.
19. W.J. Marble, R.L. Cowan and C.J. Wood, "Control of Cobalt-60 Deposition", Water Chemistry of Nuclear Reactor System 4, BNES, October, 1986.
20. 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.
21. 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.
22. 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.
23. 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. 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, B. Beverskog and P.M. Scott, "Expert Panel to Evaluate the Impact of High pH on Primary Water Stress Corrosion Cracking of Ni-Base Alloys", EPRI Summary Report, July 7, 2003.
26. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems, ANS, 2003.
27. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems, NACE, 2001.
28. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, 2001.
29. 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.
30. 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.
31. 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.
32. C.D. Thompson, D.M. Carey, and N.L. Perazzo, "Effects of Hydrogen on Electropotential Monitoring of Stress Corrosion Crack Growth", 8 Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems, ANS, p. 366, 1997.
33. P.L. Andresen, J.A. Wilson, K.S. Ahluwalia, "Use of Primary Water Chemistry in PWRs to Mitigate PWSCC of Ni-Base Alloys", Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Korea, 2006.
34. 2", EPRI MRP Report in publication.
35. D.S. Morton and M. Hansen, "The Effect of pH on Nickel Alloy SCC and Corrosion Performance," Paper 03675, Corrosion/03, NACE, 2003.
36. th Int. Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, 2003.
37. Personal communication with D.S. Morton, March 2007.
38. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors", TMS, Snowbird, August 2005.
39. 2, B/Li/pH and Zn on PWSCC of Alloy 600", EPRI Workshop on Alloy 600, Albuquerque, March 2005.
40. Noel Peat, unpublished Auger electron spectroscopy results obtained on CT specimens provided by P.L. Andresen, February 2006.
41. P.L. Andresen and M.M. Morra, "SCC of Stainless Steels and Ni Alloys in High Temperature Water", Paper 07612, Corrosion/07, NACE, 2007.
42. M.M. Morra and P.L. Andresen, unpublished results, GE Research, Schenectady, NY, 2005.