Stress corrosion cracking and crack tip characterization of alloy X-750 in boiling water reactor environments

J. P. Gibbs*, R. G. Ballinger, J. H. Jackson, Dieter Isheim, H. Hänninen

*Corresponding author for this work

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

Abstract

The stress corrosion cracking susceptibility of Inconel alloy X-750 in the HTH heat-treated condition has been evaluated in high-purity water @ 93 and 288°C under Normal Water Chemistry (NWC) and Hydrogen Water Chemistry (HWC) conditions. SCC crack growth rates of approximately 1.2×10-7 mm/s (K=28 MPa√m) under NWC conditions and 1.4×10-8 mm/s (K=28 MPa√m) under HWC conditions in 288°C high-purity water were observed. The alloy was also tested in HWC at 93°C. No SCC crack growth was observed at K= 35 MPa√m for the 525 h of testing at 93°C. At 288°C the fracture mode transitioned from predominantly transgranular cracking under fatigue conditions to intergranular cracking under constant stress intensity for both environments. Atom Probe Tomography (APT) was used to characterize the crack tip and ahead of the crack tip. The results suggest that oxygen diffuses ahead of the crack tip along specific crystallographic directions.

Original languageEnglish (US)
Title of host publication15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
PublisherJohn Wiley and Sons Inc.
Pages705-720
Number of pages16
ISBN (Print)9781622761944
StatePublished - Jan 1 2011
Event15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 - Colorado Springs, CO, United States
Duration: Aug 7 2011Aug 11 2011

Publication series

Name15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Volume1

Other

Other15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
CountryUnited States
CityColorado Springs, CO
Period8/7/118/11/11

Keywords

  • Alloy X-750
  • Atom probe tomography
  • Corrosion potential
  • Crack growth rate
  • Crack tip characterization
  • Hydrogen water chemistry
  • Normal water chemistry
  • Stress corrosion cracking

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Pollution

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  • Cite this

    Gibbs, J. P., Ballinger, R. G., Jackson, J. H., Isheim, D., & Hänninen, H. (2011). Stress corrosion cracking and crack tip characterization of alloy X-750 in boiling water reactor environments. In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 (pp. 705-720). (15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011; Vol. 1). John Wiley and Sons Inc..