The effect of strain-hardening on PWSCC of nickel-base alloys 600 and 690

Tetsuo Shoji, Zhanpeng Lu, Seiya Yamazaki

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

14 Citations (Scopus)

Abstract

Stress corrosion cracking (SCC) behavior of base metals, cold-worked base metals and heat-affected zones (HAZs) in Alloy 600MA/Alloy 182 and Alloy 690TT/Alloy 52 welds in simulated PWR primary water environments is investigated. Hardness measurements and electron backscatter diffraction measurements show a hardened area in the heat-affected zones. Grain boundary chemistries and carbide precipitations were analyzed by Auger Electron Spectroscopy of the exposed intergranular fracture surface. Alloy 690TT base metal and Alloy 690TT HAZ show high SCC resistance. Extensive IGSCC was found in the Alloy 600MA HAZ, 8% and 20% cross-rolled (2DCR) Alloy 600MA materials, while mixed intergranular/transgranular SCC was found in the 40% CR Alloy 600MA specimens. The crack growth rate in the Alloy 600MA HAZ is close to that in the 8% 2DCR base metal, which is significantly lower than that in the 20% 2DCR base metal, but significantly higher than that in the as-received Alloy 600MA base metal. Local cracking was observed in a 40% 2DCR Alloy 690TT base metal specimen. The crack growth behavior was analyzed with the theoretical model by considering the interaction between crack tip oxidation kinetics and crack tip mechanics, emphasizing the enhancing effect of stress on oxidation and the effect of strain-hardening.

Original languageEnglish
Title of host publication14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Pages220-238
Number of pages19
Publication statusPublished - 2009 Dec 1
Event14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 - Virginia Beach, VA, United States
Duration: 2009 Aug 232009 Aug 27

Publication series

Name14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
Volume1

Other

Other14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
CountryUnited States
CityVirginia Beach, VA
Period09/8/2309/8/27

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Environmental Engineering

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  • Cite this

    Shoji, T., Lu, Z., & Yamazaki, S. (2009). The effect of strain-hardening on PWSCC of nickel-base alloys 600 and 690. In 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 (pp. 220-238). (14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009; Vol. 1).