Long-term embrittlement of cast duplex stainless steels in LWR systems
- Argonne National Lab., IL (USA)
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 October 1988 to March 1989. Charpy-impact data are presented for several heats of cast stainless steel aged at temperatures between 320 and 450{degrees}C for times up to 30,000 h. Thermal aging decreases impact energy and shifts transition curves to higher temperatures. A saturation effect is observed for room-temperature impact energy and upper-self energy. Charpy data are analyzed to obtain the activation energy of the kinetics of embrittlement. The results suggest that the activation energy of embrittlement is not constant in the temperature range of 290--400{degrees}C, but increases as temperature decreases. A correlation is presented for estimating the extent of embrittlement of cast stainless steels from known material parameters. The degradation in mechanical properties can be reversed by annealing the embrittled material for 1 h at 550{degrees}C and then water quenching. 20 refs., 18 figs., 4 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Argonne National Lab., IL (USA)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5675829
- Report Number(s):
- NUREG/CR-4744-Vol.4-No.1; ANL--90/44; ON: TI91012497
- Country of Publication:
- United States
- Language:
- English
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Long-term embrittlement of cast duplex stainless steels in LWR systems
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36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
AGING
ALLOYS
ANNEALING
BWR TYPE REACTORS
CHARPY TEST
DESTRUCTIVE TESTING
DOCUMENT TYPES
EMBRITTLEMENT
FRACTURE MECHANICS
FRACTURE PROPERTIES
HEAT TREATMENTS
HIGH ALLOY STEELS
IMPACT SHOCK
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MECHANICS
PROGRESS REPORT
PWR TYPE REACTORS
REACTORS
STAINLESS STEELS
STEELS
TEMPERATURE EFFECTS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS