SCC behavior in the transitiion region of an alloy 182-SA 508 Cl.2 dissimilar weld joint under simulated BWR-NWC conditions

Qunjia Peng, Tetsuo Shoji, Stefan Ritter, Hans Peter Seifert

Research output: Chapter in Book/Report/Conference proceedingConference contribution

26 Citations (Scopus)

Abstract

Alloy 182-Low Alloy Steel (LAS) dissimilar weld joints contain the transition region that has complex microstructure. Recent incidents of stress corrosion cracking (SCC) in the weld metal of bottom head penetration housing of Boiling Water Reactors (BWR) have drawn the attention to the SCC behavior in the transition region of Alloy 182-LAS dissimilar weld joints, and in particular, to the issue whether an intergranular/interdendritic SCC crack propagating in the weld metal could easily penetrate through the fusion line into the adjacent LAS. In this study, following a microstructural characterization of the transition region of an Alloy 182-SA 508 C1.2 dissimilar weld joint, the SCC behavior in the transition region in simulated BWR-Normal Water Chemistry (NWC) environments was investigated. The results showed that the microstructure had a sharp change across the fusion line, and that the SCC propagation tended to cease at the fusion line under near-constant loading conditions. Such a SCC behavior shows consistency with the well-known SCC behavior of LAS, and with the field experience where SCC is usually confined to the Alloy 182 weld metal.

Original languageEnglish
Title of host publicationProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Pages589-599
Number of pages11
Publication statusPublished - 2005 Dec 1
Event12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States
Duration: 2005 Aug 142005 Aug 18

Publication series

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

Other

Other12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
CountryUnited States
CitySalt Lake City, UT
Period05/8/1405/8/18

Keywords

  • Alloy 182
  • Boiling Water Reactor
  • Crack Growth Rate
  • Dissimilar Weld Joint
  • Low Alloy Steel
  • Stress Corrosion Cracking

ASJC Scopus subject areas

  • Engineering(all)

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  • Cite this

    Peng, Q., Shoji, T., Ritter, S., & Seifert, H. P. (2005). SCC behavior in the transitiion region of an alloy 182-SA 508 Cl.2 dissimilar weld joint under simulated BWR-NWC conditions. In Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (pp. 589-599). (Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors).