Long-term embrittlement of cast duplex stainless steels in LWR systems. Semiannual report, October 1991--March 1992: Volume 7, No.1

Technical Report · Sat May 01 00:00:00 EDT 1993

DOI:https://doi.org/10.2172/10162138· OSTI ID:10162138

Chopra, O. K. ^[1]

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1. Argonne National Lab., IL (United States)

This progress report summarizes work performed by Argonne National Laboratory on long-term thermal embrittlement of cast duplex stainless steels in LWR systems during the six months from October 1991 to March 1992. Charpy-impact, tensile, and fracture toughness J-R curve data are presented for several heats of cast stainless steel that were aged 10,000-58,000 h at 290, 320, and 350{degree}C. The results indicate that thermal aging decreases the fracture toughness of cast stainless steels. In general, CF-3 steels are the least sensitive to thermal aging and CF-8M steels are the most sensitive. The values of fracture toughness J{sub IC} and tearing modulus for CF-8M steels can be as low as {approx}90 kJ/m{sup 2} and {approx}60, respectively. The fracture toughness data are consistent with the Charpy-impact results, i.e. unaged and aged steels that show low impact energy also exhibit lower fracture toughness. All steels reach a minimum saturation fracture toughness after thermal aging; the time to reach saturation depends on the aging temperature. The results also indicate that low-strength cast stainless steels are generally insensitive to thermal aging.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10162138
• Report Number(s): NUREG/CR-4744-Vol.7-No.1; ANL-92/42-Vol.7-No.1; ON: TI93015199; TRN: 93:015357
• Resource Relation: Other Information: PBD: May 1993
• Country of Publication: United States
• Language: English

Related Subjects

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