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Title: Prediction of aging degradation of cast stainless steel components in LWR systems

Conference ·
OSTI ID:10154056

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 of cast stainless steel components during reactor service are presented. A common ``predicted 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:
Argonne National Lab., IL (United States)
Sponsoring Organization:
Nuclear Regulatory Commission, Washington, DC (United States)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
10154056
Report Number(s):
ANL/CP-75791; CONF-920375-24; ON: DE92014848
Resource Relation:
Conference: Aging research information conference,Rockville, MD (United States),24-27 Mar 1992; Other Information: PBD: Mar 1992
Country of Publication:
United States
Language:
English