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.2015.06.025Additional 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48034476
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- CHROMIUM; CRACKING; DEFORMATION; GRAIN BOUNDARIES; HARDNESS; HEAT; HEAT AFFECTED ZONE; INCONEL 690; NICKEL BASE ALLOYS; PWR TYPE REACTORS; STRESS CORROSION; STRESSES; TEMPERATURE RANGE 0400-1000 K; VICKERS HARDNESS; WATER; WELDED JOINTS; WELDING
- Descriptors DEC
- ALLOY-NI59CR30FE9; ALLOYS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; DECOMPOSITION; ELEMENTS; ENERGY; ENRICHED URANIUM REACTORS; FABRICATION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HYDROGEN COMPOUNDS; INCONEL ALLOYS; IRON ALLOYS; JOINING; JOINTS; MATERIALS; MECHANICAL PROPERTIES; METALS; MICROSTRUCTURE; NICKEL ALLOYS; NICKEL BASE ALLOYS; OXYGEN COMPOUNDS; POWER REACTORS; PYROLYSIS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZONES
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.