Effects of Pb on SCC of Alloy 600 and Alloy 690 in prototypical steam generator chemistries

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

Volumn , Issue , 2005, Pages 1229-1242

  Lumsden, Jesse ^a   McIlree, Allan ^b   Eaker, Richard ^c   Thompson, Rocky ^d   Slosnerick, Steve ^e  

^a ROCKWELL SCIENTIFIC COMPANY   (United States)

^b ELECTRIC POWER RESEARCH INSTITUTE   (United States)

^c DUKE ENERGY   (United States)

^d Florida Power Corporation   (United States)

^e First Energy   (United States)

Author keywords

Alloy 600; Alloy 690; Corrosion potential; Intergranular corrosion; Lead cracking; Once through steam generators; Steam generators; Stress corrosion cracking

Indexed keywords

DEGRADATION; ELECTROCHEMISTRY; LEAD; STEAM GENERATORS; THIN FILMS; TUBES (COMPONENTS);

ALLOY 600; ALLOY 690; CORROSION POTENTIAL; INTERGRANULAR CORROSION; LEAD CRACKING; ONCE THROUGH STEAM GENERATORS;

STRESS CORROSION CRACKING;

EID: 33745200954     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (19)

1. P. A. Sherburne: Surface Analysis of Oconee Unit 1 Steam Generator Tubes, Proceedings: 1996 EPRI Surface Chemistry Workshop, TR-112481.
2. J. B. Lumsden: Insights on Local Chemistry and IGA/SCC from Surface Analysis of Pulled Tubes, Proceedings: 1996 EPRI Surface Chemistry Workshop, TR-112481.
3. D. P. Rochester and R. W. Eaker: Laboratory Examination Results from Oconee Nuclear Station Once through Steam Generator Tubes, 9th Environ. Degrad., TMS, 2000, p.639.
4. L. E. Thomas, V. Y. Gertsman and S. M. Bruemmer: Crack-Tip Microstructures and Impurities in Stress-Corrosion-Cracked Alloy 600 from Recirculating and Once-Through Steam Generators, 10th Environ. Degrad., NACE, 2002.
5. L. Thomas and S. Bruemmer: Analytical Electron Microscopy of Intergranular Attack and Stress Corrosion Cracks in Alloy 600 Tubes Removed from Recirculating Steam Generators, EPRI, Palo Alto, CA: 2003, 1003587.
6. L. Thomas and S. Bruemmer: Analytical Electron Microscopy of Pulled Alloy 600 Steam Generator Tubes from Comanche Peak Unit 1 and Seabrook Unit 1, EPRI, Palo Alto, CA: 2004, 1009346.
7. R. W. Staehle: Assessment of and Proposal for a Mechanistic Interpretation of the SCC of High Nickel Alloys in Lead-Containing Environments, 11th Environ. Degrad. ANS, 2003, p.381.
8. H. R. Copson and S. W. Dean: Effect of Contaminants on Resistance to Stress Corrosion Cracking of Ni-Cr Alloy 600 in Pressurized Water, Corrosion 21, 1 (1965).
9. G. P. Airey: Effect of Carbon Content and Thermal treatment on the SCC Behavior of Inconel 600 Steam Generator Tubing, Corrosion 35, 129 (1979).
10. G. O. Hayner, et al.: Examination of Tubes Removed from St. Lucie Unit 1 and Investigation of Causes of the Corrosion, 3rd Environ. Degrad., TMS, 1988, p 449.
11. A. Agrawal and J. P.N. Paine: Lead Cracking in Alloy 600-A Review, 3rd Environ. Degrad., NACE, 1990, p. 7-1.
12. B. P. Miglin and J. M. Sarver: Investigation of Lead as a Cause of Stress Corrosion Cracking at Support Plate Intersections, NP-7367, EPRI, Palo Alto, CA, 1991.
13. th Environ. Degrad. of Materials in Nuclear Power Systems-Water Reactors, ANS, 1997, p. 216.
14. th Environ. Degrad., ANS, 2003, p.381.
15. D. van Rooyen: Review of Stress Corrosion Cracking of Inconel 600, Corrosion, 597, 31 (1975).
16. W. H. Cullen and M. J. Partridge: Susceptibility of Alloys 600 and 690 to Acidified Sulfate and Chloride Environments, EPRI, Palo Alto, CA, TR-104045, 1994.
17. M. Helie, I. Lambert, and G. Santarini: Some Considerations about the Possible Mechanisms of Lead Assisted Stress Corrosion Cracking of Steam Generator Tubing, 7th Environ. Degrad., NACE, 1995, p.247.
18. nd Environ. Degrad., ANS, 1985, p. 293.
19. S. M. Bruemmer.: Interfacial Precipitation, Segregation and Deformation in Alloy 600: Implication on Primary-Side IGSCC, EPRI TR-104898, December 1996