Published October 2015 | Version v1
Journal article

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

  • 1. State Key Laboratory of Advanced Special Steels, Shanghai University, Shanghai 200072 (China)
  • 2. Institute of Materials Science, School of Materials Science and Engineering, Shanghai University, Shanghai 200072 (China)
  • 3. New Industry Creation Hatchery Center, Tohoku University, Sendai 980-8579 (Japan)

Description

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. - Highlights: • High Vickers hardness and KAM near the Alloy 690 weld fusion line. • Low fraction of Σ3 boundaries near the fusion line. • High grain boundary chromium content in Alloy 690 HAZ. • Higher SCC resistance in Alloy 690 HAZ than in Alloy 600 HAZ. • Locally intergranular PWSCC in 40% cross-rolled Alloy 690.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2015.06.025

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2015.06.025;
PII
S0022-3115(15)30050-7;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
465
Journal Page Range
p. 471-481
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.