Characterization of microstructure, local deformation and microchemistry in Alloy 690 heat-affected zone and stress corrosion cracking in high temperature water

Zhanpeng Lu, Junjie Chen, Tetsuo Shoji, Yoichi Takeda, Seiya Yamazaki

Research output: Contribution to journalArticlepeer-review

14 Citations (Scopus)

Abstract

With increasing the distance from the weld fusion line in an Alloy 690 heat-affected zone, micro-hardness decreases, kernel average misorientation decreases and the fraction of Σ3 boundaries increases. Chromium depletion at grain boundaries in the Alloy 690 heat-affected zone is less significant than that in an Alloy 600 heat-affected zone. Alloy 690 heat-affected zone exhibits much higher IGSCC resistance than Alloy 600 heat-affected zone in simulated pressurized water reactor primary water. Heavily cold worked Alloy 690 exhibits localized intergranular stress corrosion cracking. The effects of metallurgical and mechanical properties on stress corrosion cracking in Alloy 690 are discussed.

Original languageEnglish
Pages (from-to)471-481
Number of pages11
JournalJournal of Nuclear Materials
Volume465
DOIs
Publication statusPublished - 2015 Jun 29

Keywords

  • Heat-affected zone
  • High temperature water
  • Nickel-base alloy
  • Pressurized water reactor
  • Stress corrosion cracking
  • Welding

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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