Long-term embrittlement of cast duplex stainless steels in LWR systems
- Argonne National Lab., IL (United States)
This progress report summarizes work performed by Argonne National Laboratory on long-term embrittlement of cast duplex stainless steels in LWR systems during the six months from April to September 1991. A procedure and correlations are presented for predicting Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, and J[sub IC] of aged cast stainless steels from known material information. The saturation'' impact strength and fracture toughness of a specific cast stainless steel, i.e., the minimum value that would be achieved for the material after long-term service, is estimated from the chemical composition of the steel. Mechanical properties as a function of time and temperature of reactor service are estimated from impact energy and flow stress of the unaged material and the kinetics of embrittlement, which are also determined from chemical composition. The J[sub IC] values are determined from the estimated J-R curve and flow stress. Examples of estimating mechanical properties of cast stainless steel components during reactor service are presented. A common lower-bound'' J-R curve for cast stainless steels of unknown chemical composition is also defined for a given grade of steel, ferrite content, and temperature.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Argonne National Lab., IL (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 7190283
- Report Number(s):
- NUREG/CR-4744-Vol.6-No.2; ANL--92/32; ON: TI93004790
- Country of Publication:
- United States
- Language:
- English
Similar Records
Long-term embrittlement of cast duplex stainless steels in LWR systems. Semiannual report, April--September 1991, Volume 6, No. 2
Prediction of aging degradation of cast stainless steel components in LWR systems
Related Subjects
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
AGING
ALLOYS
CHARPY TEST
DESTRUCTIVE TESTING
DOCUMENT TYPES
EMBRITTLEMENT
FRACTURE PROPERTIES
HIGH ALLOY STEELS
IMPACT STRENGTH
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
PROGRESS REPORT
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
STAINLESS STEELS
STEELS
STRESSES
TENSILE PROPERTIES
TESTING
THERMAL DEGRADATION
THERMAL STRESSES
WATER COOLED REACTORS