Long-term embrittlement of cast duplex stainless steels in LWR systems. Annual report, October 1983-September 1984
Technical Report
·
OSTI ID:5625570
A program is being conducted to investigate the significance of in-service embrittlement of cast duplex stainless steels under light-water reactor operating conditions. The existing data are evaluated to determine the expected embrittlement of cast components during the operating lifetime of reactors and to define the objectives and scope of the investigation. Data for the metallurgical characterization of the various cast stainless steels used in the investigation are presented. Charpy impact tests on short-term aged material indicate that CF-3 stainless steels are less susceptible to embrittlement than CF-8 or CF-8M stainless steels. Embrittlement of the ferrite phase is primarily due to pinning of the dislocations by two of these precipitates, designed as Type M and Type X. The ferrite phase is embrittled after approx.8 yr at 300/sup 0/C and shows cleavage fracture. Examination of the fracture surfaces of the impact-test specimens indicates that the toughness of the long-term aged material is determined by the austenite phase. 5 refs., 7 figs., 6 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5625570
- Report Number(s):
- NUREG/CR-4204; ANL-85-20; ON: TI85011158
- Country of Publication:
- United States
- Language:
- English
Similar Records
Aging of cast duplex stainless steels in LWR systems
Initial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems
Long-term embrittlement of cast duplex stainless steels in LWR systems: Semiannual report, April--September 1987
Conference
·
Mon Oct 01 00:00:00 EDT 1984
·
OSTI ID:6410369
Initial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems
Technical Report
·
Wed Aug 01 00:00:00 EDT 1990
·
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Long-term embrittlement of cast duplex stainless steels in LWR systems: Semiannual report, April--September 1987
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·
Tue Aug 01 00:00:00 EDT 1989
·
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
BWR TYPE REACTORS
CARBON ADDITIONS
CHARPY TEST
CHEMICAL COMPOSITION
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
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DUCTILE-BRITTLE TRANSITIONS
DUCTILITY
EMBRITTLEMENT
FERRITE
GRAIN ORIENTATION
HARDNESS
HIGH TEMPERATURE
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MICROSTRUCTURE
ORIENTATION
PHYSICAL PROPERTIES
PIPES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
TESTING
THERMODYNAMIC PROPERTIES
TRANSITION TEMPERATURE
ULTIMATE STRENGTH
WATER COOLED REACTORS
WATER MODERATED REACTORS
YIELD STRENGTH
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
BWR TYPE REACTORS
CARBON ADDITIONS
CHARPY TEST
CHEMICAL COMPOSITION
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DESTRUCTIVE TESTING
DUCTILE-BRITTLE TRANSITIONS
DUCTILITY
EMBRITTLEMENT
FERRITE
GRAIN ORIENTATION
HARDNESS
HIGH TEMPERATURE
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MICROSTRUCTURE
ORIENTATION
PHYSICAL PROPERTIES
PIPES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
TESTING
THERMODYNAMIC PROPERTIES
TRANSITION TEMPERATURE
ULTIMATE STRENGTH
WATER COOLED REACTORS
WATER MODERATED REACTORS
YIELD STRENGTH