Thermal aging of cast stainless steels in LWR systems: Estimation of mechanical properties

Conference · Fri Nov 01 00:00:00 EST 1991

DOI:https://doi.org/10.2172/5561283· OSTI ID:10142049

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 ``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: 10142049
• Report Number(s): ANL/CP-73465; CONF-920631-28; ON: DE92012654
• Resource Relation: Conference: American Society of Mechanical Engineers (ASME) pressure vessels and piping conference,New Orleans, LA (United States),21-25 Jun 1992; Other Information: PBD: Nov 1991
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
STAINLESS STEELS
AGING
MECHANICAL PROPERTIES
PWR TYPE REACTORS
BWR TYPE REACTORS
FRACTURE PROPERTIES
CHARPY TEST
EMBRITTLEMENT
REACTOR COMPONENTS
210100
210200
360103
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED