Estimation of mechanical properties of cast stainless steels during thermal aging in LWR systems

Technical Report · Tue Oct 01 04:00:00 EDT 1991

DOI:https://doi.org/10.2172/142528· OSTI ID:142528

Chopra, O K

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 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). Materials and Components Technology Div.
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 142528
• Report Number(s): ANL/MCT/PP--74905; ON: DE94008471
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
DATA
EMBRITTLEMENT
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
PROBABILISTIC ESTIMATION
REACTOR MATERIALS
STAINLESS STEELS
TEMPERATURE DEPENDENCE
TENSILE PROPERTIES
WATER COOLED REACTORS