Microstructural and microchemical characterization of primary-side Cracks in an Alloy 600 nozzle head penetration and its Alloy 182 j-weld from the Davis-Besse reactor vessel

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

Volumn , Issue , 2005, Pages 567-578

  Thomas, Larry ^a   Johnson, Brad R ^a   Vetrano, John S ^a   Bruemmer, Stephen M ^a  

^a PACIFIC NORTHWEST NATIONAL LABORATORY   (United States)

Author keywords

Alloy 182; Alloy 600; Cracking; PWSCC; Weld micro structures

Indexed keywords

CARBIDES; CHROMIUM; CORROSION; CRACKS; GRAIN BOUNDARIES; METALLOGRAPHIC MICROSTRUCTURE; NOZZLES; NUCLEAR INSTRUMENTATION; PRESSURIZED WATER REACTORS; TITANIUM; TRANSMISSION ELECTRON MICROSCOPY; WELDS;

ALLOY 182; ALLOY 600; CRACKING; PWSCC; WELD MICRO STRUCTURES;

NICKEL ALLOYS;

EID: 33745195002     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (11)

1. R.S Pathania, A.R. McIlree and J. Hickling, "Overview of Primary Water Cracking of Alloys 182/82 in PWRs," pp. 13-27 in Proc. Fontevraud V International Symposium: Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors," SFEN, Paris, 2002.
2. W. Bamford and J. Hall "A Review of Alloy 600 Cracking in Operating Nuclear Plants: Historical Experience and Future Trends," pp. 1071- 1080 in Proc. of the Eleventh International Conference of Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ANS, Illinois, 2003.
3. M.R. Robinson, D.E. Whitaker, M.L. Arey and S. Fyfitch, "Recent CRDM Nozzle PWSCC Experience at the Oconee Nuclear Station," Proc. of the Eleventh International Conference of Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Ibid 1.
4. H. Xu, S. Fyfitch, J.W. Hyres, T.A. Lang and T.T Pleune, "Laboratory Investigation of PWSCC of CRDM Nozzle 3 and its J-Groove Weld on the Davis-Besse Reactor Vessel Head," These proceedings.
5. 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, " Laboratory Investigation of PWSCC of CRDM Nozzle 3 and Its J-Groove Weld on the Davis-besse Reactor Vessel Head Ibid 2.
6. L. E. Thomas and S. M. Bruemmer, Corrosion. J., 2000, 56, 572.
7. L. E. Thomas, J. S. Vetrano, S. M. Bruemmer, P. Efsing, B. Forssgren, G. Embring and K. Gott," High-Resolution Analytical Electron Microscopy Characterization of Environmentally Assisted Cracks in Alloy 182 Weldments," Corrosion. J. Ibid 2.
8. O.K. Chopra, B. Alexandreau and W.J Shack, "Crack Growth Rates of Alloy 600 from the Davis Besse Reactor CRDM Nozzle #3 in PWR Environment," Proceedings of PVP 2005. 2005 ASME Pressure Vessel and Piping Division Conference, July 17-21, 2005 Denver, Colorado, USA.
9. A. Jenssen, K. Norrgard, J. Lagerstrom, G. Embring and D. Tice, "Cracking in Dissimilar Metal Welds," Proceedings of PVP 2005. 2005 ASME Pressure Vessel and Piping Division Conference Ibid 2.
10. L. E. Thomas and S. M. Bruemmer, "Observations and Insights into Pb-Assisted Stress Corrosion Cracking of Alloy 600 Steam Generator Tubes," These proceedings.
11. , L. E. Thomas, S. M. Bruemmer and P.M. Scott, "Analytical TEM Comparisons of Stress-Corrosion-Crack Microstructures in Alloy 600 under Steam-Generator Service and Laboratory Test Conditions," pp. 1037-48, Observations and Insights into Pb-Assisted Stress Corrosion Cracking of Alloy 600 Steam Generator Tubes Ibid 1.