Stress corrosion cracking susceptibility of AISI 316 NG and 316 stainless steel in an impurity environment
The relative stress corrosion cracking (SCC) susceptibility of heat-treated AISI 316 nuclear grade (NG) and 316 stainless steel (SS) has been investigated by means of constant extension rate tensile (CERT) tests over a range of strain rates from 10/sup -5/ to 10/sup -7/ s/sup -1/ in simulated boiling water reactor (BWR) environments that contain SO/sub 4//sup 2 -/ as an impurity. It is observed that although AISI 316 NG SS is extremely resistant to integranular SCC (IGSCC) even when subjected to severe heat treatments, it can become susceptible to transgranular SCC (TGSCC) in the presence of impurities. Sensitized AISI 316 SS, however, is susceptible to IGSCC even in high-purity water containing 0.2 ppm O/sub 2/ and the addition of an impurity aggravates the IGSCC susceptibility. The SCC results obtained for both materials are discussed in terms of a phenomenological model that incorporates a slip-dissolution mechanism and elastic-plastic fracture mechanics. The results for both IGSCC and TGSCC are demonstrated to be consistent with the slip-dissolution model of Ford.
- Research Organization:
- Argonne National Laboratory, Argonne, IL
- OSTI ID:
- 5987016
- Journal Information:
- Corrosion (Houston); (United States), Journal Name: Corrosion (Houston); (United States) Vol. 41:11; ISSN CORRA
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
BOILERS
BWR TYPE REACTORS
CHALCOGENIDES
CHEMICAL REACTIONS
CORROSION
CORROSION RESISTANCE
CRACKS
DESTRUCTIVE TESTING
DISSOLUTION
FRACTURE MECHANICS
FRACTURE PROPERTIES
HEAT TREATMENTS
IMPURITIES
INTERGRANULAR CORROSION
MATERIALS TESTING
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICS
OXIDES
OXYGEN COMPOUNDS
REACTORS
SIMULATION
SLIP
STEEL-CR17NI12MO3
STRAIN RATE
STRESS CORROSION
SULFUR COMPOUNDS
SULFUR OXIDES
TEMPERATURE DEPENDENCE
TENSILE PROPERTIES
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS