Factors influencing SCC and IASCC of stainless steels in high temperature water

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 479, Issue , 2004, Pages 185-192

  Andresen, Peter L ^a  

^a GE GLOBAL RESEARCH   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

HIGH TEMPERATURE WATER; SENSITIZATION; WATER CHEMISTRY; WATER QUENCH;

CRACK PROPAGATION; GRAIN BOUNDARIES; IRRADIATION; MATHEMATICAL MODELS; STRESS CORROSION CRACKING; TEMPERATURE MEASUREMENT; WATER;

STAINLESS STEEL;

EID: 7744234170     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2004-2663     Document Type: Conference Paper

References (34)

1. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 1983 - 2001, NACE / ANS / TMS.
2. Ford, F.P. and Andresen, P.L., 1994, "Corrosion in Nuclear Systems: Environmentally Assisted Cracking in Light Water Reactors," in Corrosion Mechanisms, Ed. P. Marcus and J. Ouder, Marcel Dekker, pp.501-546.
3. Andresen, P.L. and Ford, F.P., 1988, "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.
4. Ford, F.P., Taylor, D.F., Andresen, P.L. and Ballinger, R.G., 1987, "Corrosion Assisted Cracking of Stainless and Low Alloy Steels in LWR Environments," EPRI Contract RP2006-6, Report NP5064M.
5. Andresen, P.L., 2001, "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.
6. Andresen, P.L., 1996, "Conceptual Similarities and Common Predictive Approaches for SCC in High Temperature Water Systems", Paper 96258, Corrosion/96, NACE.
7. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, pp. 1-83 to 1-121.
8. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, pp.579-596.
9. Andresen, P.L. and Ford, F.P., 1996, "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.
10. Andresen, P.L. and Briant, C.L., 1989, "Environmentally Assisted Cracking of Types 304L/316L/316NG Stainless Steel in 288°C Water," Corrosion, Vol. 45, pp. 448-463.
11. Andresen, P.L. and Briant, C.L., 1988, "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.
12. Andresen, P.L., 1988, "Environmentally Assisted Growth Rate Response of Nonsensitized AISI 316 Grade Stainless Steels in High Temperature Water," Corrosion, Vol 44, 7, pp. 450.
13. Andresen P.L., 1981, "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.
14. Andresen P.L., 1981, "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.
15. Niedrach, L.W., 1980, "A New Membrane Type pH Sensor for Use in High Temperature High Pressure Water," J. Electrochem. Soc., Vol 127, pp. 2122.
16. Andresen, P.L., Angeliu, T.M. and Young, L.M., 2001, "Immunity, Thresholds, and Other SCC Fiction," Proc. Staehle Symp. on Chemistry & Electrochem. of Corrosion & SCC, TMS.
17. Andresen, P.L., 1999, "SCC Testing and Data Quality Considerations," Ninth Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME. See also, Andresen, P.L., January 30, 1998, "Experimental Quality Guidelines for SCC Testing", GE CRD.
18. Andresen, P.L., 1999, "SCC Testing and Data Quality Considerations," Ninth Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME. See also, Andresen, P.L., January 30, 1998, "Experimental Quality Guidelines for SCC Testing", GE CRD.
19. Andresen, P.L., Gott, K. and Nelson, J.L., 1999, "Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel in 288C Water: A Five Laboratory Round Robin," Proc. Ninth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME.
20. Andresen, P.L., Angeliu, T.M., Young, L.M., Catlin, W.R., and Horn, R.M., 2001, "Mechanisms and Kinetics of SCC in Stainless Steels," Proc. Tenth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems, NACE.
21. Andresen, P.L., Angeliu, T.M., Catlin, W.R., Young, L.M. and Horn, R.M., 2000, "Effect of Deformation on SCC of Unsensitized Stainless Steel," Corrosion/2000, Paper #00203, NACE.
22. Andresen, P.L., Angeliu, T.M. and Young, L.M., 2001, "Effect of Martensite & Hydrogen on SCC of Stainless Steels," Paper #01228, Corrosion/01, NACE.
23. Andresen, P.L., Young, L.M., Emigh, P.W. and Horn, R.M., 2002, "Stress Corrosion Crack Growth Rate Behavior of Ni Alloys 182 and 600 in High Temp. Water," Corrosion/02, Paper 02510, NACE.
24. Arioka, K., Kanashima, Y., Yamada, T. and Terachi, T., 2003, "Influence of Boric Acid, Hydrogen Concentration and Grain Boundary Carbides on IGSCC Behaviors of SUS 316 Under PWR Primary Water," Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems, ANS.
25. Tsutsumi, K., 2002, et al, "Fatigue Life Reduction in PWR Water Environments for Stainless Steel," PVP Conf. Volume 410-2, ASME, pp.23-34.
26. Solomon, H.D. and DeLair, R.E., 2003, unpublished data on low cycle fatigue crack initiation in Stainless Steels, GECRD.
27. Kim, Y.J. and Andresen, P.L., 2001, "Data Quality, Issues and Guidelines for ECP Measurements in High Temperature Water," Corrosion/2001, Paper #01137, NACE.
28. Morton, D.S., Attanasio, S.A., Fish, J.S., and Schurman, M.K., 1999, "Influence of Dissolved Hydrogen on Nickel Alloy SCC in High Temperature Water," Corrosion/99, Paper #99447, NACE.
29. Andresen, P.L., 2002, "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.
30. Andresen, Pi., Emigh, P.W., Morra, M.M. and Horn, R.M., 2003, "Alloy X750 Stress Corrosion Crack Growth Rate Behavior in High Temperature Water," Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems, ANS.
31. Angeliu, T.M., Andresen, P.L., Sutliff, J.A. and Horn, R.M., 1999, "Intergranular Stress Corrosion Cracking of Unsensitized Stainless Steels in BWR Environments," Proc. Ninth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME, pp.311-318.
32. Angeliu, T.M., Andresen, P.L., Hall, E., Sutliff, J.A., Sitzman, S., 2000, "Strain and Microstructure Characterization of Austenitic Stainless Steel Weld HAZs," Corrosion/2000, Paper #00186, NACE.
33. Andresen, P.L., 1994, "Effect of Noble Metal Coating & Alloying on the Stress Corrosion Crack Growth Rate of Stainless Steel in 288C Water," Proc. Sixth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME, pp.245-253.
34. th Int Symp on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME, p.277-285.