Probabilistic interpretation of SCC initiation and growth

NACE - International Corrosion Conference Series

Volumn 1999-April, Issue , 1999, Pages

  Andresen, Peter L ^a  

^a GE GLOBAL RESEARCH   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

LOAD TESTING;

CONSTANT LOADS; INITIATION SITES; LABORATORY TESTING; LOW PROBABILITY; PROBABILISTIC INTERPRETATION; SCC INITIATION; STRESS INTENSITY; WATER CHEMISTRY;

STRESS CORROSION CRACKING;

EID: 84884720173     PISSN: 03614409     EISSN: None     Source Type: Book Series    
DOI: None     Document Type: Conference Paper

References (26)

1. 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.
2. F.P. Ford, D.F. Taylor, P.L. Andresen, and R.G. Ballinger, "Environmentally Controlled Cracking of Stainless and Low Alloy Steels in Light Water Reactor Environments," RP 2006-6, EPRI Supplemental Report NP5064, 1987.
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, p. 167-183, 1988.
4. R.N. Parkins, "Mechanistic Aspects of Stress Corrosion Cracking", in Parkins Symposium on Fundamental Aspects of Stress Corrosion Cracking, Eds. S.M. Bruemmer et al., TMS, p3-42, 1992.
5. P.L. Andresen, L.P. Vasatis & F.P. Ford, "Behavior of Short Cracks in Stainless Steel at 288C", Paper #495, Corrosion/90, NACE, Houston, 1990.
6. R. Magdowski and M.O. Speidel, "Effect of Cold Work on the Growth Rates of SCC in Structural Materials of Nuclear Systems", Paper #112, Corrosion/96, NACE, 1996.
7. See also M.O. Speidel and R. Magdowski, "SCC of Nickel Base Alloys in High Temperature Water", Proc. Sixth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, p.361, 1993.
8. P.L. Andresen and T.M. Angeliu, Unpublished crack growth rate data on cold worked and annealed stainless steel in 288C water, GE Corp. Research and Development Center, Schenectady, NY, 1998.
9. C.L. Briant and A.M. Ritter, "The Effect of Cold Work on the Sensitization of 304 Stainless Steel", Scripta Metallurgica 13, p. 177-181, 1979.
10. See also C.L. Briant and A.M. Ritter, "The Effect of Deformation Induced Martensite on the Sensitization of Austenitic Stainless Steels", Metallurgical Trans A, 11A, p. 2009-2017, 1980.
11. P.L. Andresen and L.M. Young, "Characterization of the Roles of Electrochemistry, Convection and Crack Chemistry in Stress Corrosion Cracking", Proc. Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, p. 579-596, 1995.
12. See also P.L. Andresen, "Effects of Flow Rate on SCC Growth Rate Behavior in BWR Water", Proc. Eighth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, AIME, 1998.
13. P.L. Andresen, "Modelling of Water and Material Chemistry Effect on Crack Tip Chemistry and Resulting Crack Growth Rate Kinetics", Proc. Third Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, 1988, pp. 301-312.
14. P.L. Andresen, "Conceptual Similarities and Common Predictive Approaches for SCC in High Temperature Water Systems", Paper 96258, Corrosion/96, NACE, 1996.
15. P.L. Andresen, "Irradiation Assisted Stress Corrosion Cracking", in Book on Stress Corrosion Cracking: Materials Performance and Evaluation, Ed. R.H. Jones, ASM, Materials Park, 1992, p. 181-210.
16. S.M. Bruemmer, E.P. Simonen, P.M. Scott, P.L. Andresen, G.S. Was, and J.L. Nelson, "Radiation Induced Material Changes and Susceptibility to Intergranular Failure of Light Water Reactor Core Internals", submitted to J of Nuclear Materials, Oct 1998.
17. P.L. Andresen, "Effects of Testing Characteristics on Observed SCC Behavior in BWRs", Paper #98137, Corrosion/98, NACE, 1998.
18. P.L. Andresen, "Executive Summary: IGSCC Crack Growth Rate Measurements in BWR Environments. An SKI / EPRI Round Robin on Stress Corrosion Cracking of Sensitized 304 Stainless Steel", Report to K. Gott, SKI, Stockholm, Sept 23, 1998. See also the final reports by each participating laboratory.
19. P.L. Andresen, Unpublished data on Alloy 600 and Alloy 182 weld metal, GE CRD, 1998.
20. L.G. Ljungberg, D. Cubicciotti, and M. Trolle, "Crack Propagation in Alloys 600 and 182 in Simulated BWR Environment", Proc. Fifth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, p. 226-234, 1992.
21. See also L.G. Ljungberg, "Study on Environmental Cracking in Simulated BWR Water", Project RP2293-1, EPRI, Palo Alto, 1992.
22. S. Suresh and R.O. Ritchie, "Near-Threshold Fatigue Crack Propagation: A Perspective on the Role of Crack Closure" (and other papers) in "Fatigue Crack Growth Threshold Concepts", Eds. D.L. Davidson and S. Suresh, TMS, 1984.
23. "Mechanics of Fatigue Crack Closure", J.C. Newman Jr and W. Elber, Eds., STP 982, ASTM, Philadelphia, 1988.
24. th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, p. 61-69, 1993.
25. S. Suzuki and T. Shoji, "Characteristics of the SCC Surface Crack Growth Behavior in Low K Region in Oxygenated High Temperature Water," Proc. 8th Int Symp on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, p. 685-694, 1997.
26. P.L. Andresen, "Observation and Prediction of the Effects of Water Chemistry and Mechanics on Environmentally Assisted Cracking of Inconels 182 Weld Metal and 600", Corrosion 44, p. 376-385, 1988.