Influence of chromium depletion on IGSCC of 304 stainless steel
Conference
·
OSTI ID:5704163
Direct correlations are made between the extent of chromium depletion at grain boundaries and intergranular stress corrosion cracking (IGSCC) of 304 stainless steel during slow-strain-rate (SSR) tensile tests in 288 C aerated water. IGSCC was found to depend on the minimum chromium concentration, the spacing of carbides and the width of chromium depleted zone at grain boundaries. Modifying any one of these interfacial characteristics impacted IG cracking and ductility. Under the conditions of the SSR test, IGSCC is sharply increased as the grain boundary chromium concentration drops below {approximately}13.5 wt%. The presence of a semi-continuous distribution of carbides at grain boundaries prompted some IG cracking and ductility loss without significant chromium depletion. This cracking was eliminated by heat treating to form isolated carbides at boundaries. Very narrow chromium depletion widths (<4 nm) enhanced IGSCC over that observed for stainless steel with semi-continuous carbides. The extent of IG cracking and the degree of embrittlement also increased with the width of the chromium depletion zone. 20 refs., 7 figs., 2 tabs.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5704163
- Report Number(s):
- PNL-SA-18771; CONF-9104259--1; ON: DE91012774
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Technical Report
·
Sun Aug 01 00:00:00 EDT 1993
·
OSTI ID:10109463
Distributions of Cr depletion levels in sensitized AISI 304 stainless steel and its implications concerning intergranular corrosion phenomena
Journal Article
·
Tue Nov 30 23:00:00 EST 1993
· Journal of the Electrochemical Society
·
OSTI ID:142181
Radiation hardening and radiation-induced chromium depletion effects on intergranular stress corrosion cracking of austenitic stainless steels
Conference
·
Sun Feb 28 23:00:00 EST 1993
·
OSTI ID:6787431
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
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CRYSTAL STRUCTURE
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HEAT RESISTING ALLOYS
HEAT TREATMENTS
HIGH ALLOY STEELS
IMAGES
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
METALS
MICROSCOPY
MICROSTRUCTURE
NICKEL ALLOYS
REACTORS
SCANNING ELECTRON MICROSCOPY
STAINLESS STEEL-304
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STEEL-CR19NI10
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36 MATERIALS SCIENCE
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BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRYSTAL STRUCTURE
ELECTRON MICROSCOPY
ELEMENTS
GRAIN BOUNDARIES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TREATMENTS
HIGH ALLOY STEELS
IMAGES
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
METALS
MICROSCOPY
MICROSTRUCTURE
NICKEL ALLOYS
REACTORS
SCANNING ELECTRON MICROSCOPY
STAINLESS STEEL-304
STAINLESS STEELS
STEEL-CR19NI10
STEELS
STRESS CORROSION
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS