Prediction of environmental and strain-rate effects on the stress corrosion cracking of austenitic stainless steels
The stress corrosion cracking (SCC) susceptibility of austenitic stainless steels in high-temperature water is controlled by environmental variables (e.g., dissolved oxygen, corrosion potential, impurities), microstructure (e.g., degree of sensitization), and strain rate. A phenomenological model based on the slip-dissolution mechanism and elastic-plastic fracture mechanics is presented to quantitatively describe the effects of both environment-related parameters and strain rate on SCC in constant extension rate tests. The model predictions are in good agreement with the results of tests performed on Types 304, 316, and 316NG stainless steel at different strain rates in a wide variety of environments relevant to boiling-water reactors.
- Research Organization:
- Materials Science and Technology Div., Argonne National Lab., Argonne, IL 60439
- OSTI ID:
- 6524482
- Journal Information:
- J. Pressure Vessel Technol.; (United States), Journal Name: J. Pressure Vessel Technol.; (United States) Vol. 109:1; ISSN JPVTA
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION
CORROSION RESISTANT ALLOYS
CORROSIVE EFFECTS
CRACK PROPAGATION
CRYSTAL STRUCTURE
DISSOLVED GASES
ELASTICITY
ELEMENTS
FEEDWATER
FLUIDS
FRACTURE MECHANICS
GASES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HYDROGEN COMPOUNDS
IMPURITIES
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICS
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONMETALS
OXYGEN
OXYGEN COMPOUNDS
PLASTICITY
REACTOR MATERIALS
REACTORS
SLIP
SOLUTES
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRAIN RATE
STRESS CORROSION
TENSILE PROPERTIES
TESTING
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS