Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Long-term embrittlement of cast duplex stainless steels in LWR systems. Annual report, October 1983-September 1984

Technical Report ·
OSTI ID:5625570
A program is being conducted to investigate the significance of in-service embrittlement of cast duplex stainless steels under light-water reactor operating conditions. The existing data are evaluated to determine the expected embrittlement of cast components during the operating lifetime of reactors and to define the objectives and scope of the investigation. Data for the metallurgical characterization of the various cast stainless steels used in the investigation are presented. Charpy impact tests on short-term aged material indicate that CF-3 stainless steels are less susceptible to embrittlement than CF-8 or CF-8M stainless steels. Embrittlement of the ferrite phase is primarily due to pinning of the dislocations by two of these precipitates, designed as Type M and Type X. The ferrite phase is embrittled after approx.8 yr at 300/sup 0/C and shows cleavage fracture. Examination of the fracture surfaces of the impact-test specimens indicates that the toughness of the long-term aged material is determined by the austenite phase. 5 refs., 7 figs., 6 tabs.
Research Organization:
Argonne National Lab., IL (USA)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
5625570
Report Number(s):
NUREG/CR-4204; ANL-85-20; ON: TI85011158
Country of Publication:
United States
Language:
English