Aging degradation of cast stainless steel
Abstract
A program is being conducted to investigate the significance of in-service embrittlement of cast-duplex stainless steels under light-water reactor operating conditions. Data from room-temperature Charpy-impact tests for several heats of cast stainless steel aged up to 10,000 h at 350, 400, and 450/sup 0/C are presented and compared with results from other studies. Microstructures of cast-duplex stainless steels subjected to long-term aging either in the laboratory or in reactor service have been characterized. The results indicate that at least two processes contribute to the low-temperature embrittleent of duplex stainless steels, viz., weakening of the ferrite/austenite phase boundary by carbide precipitation and embrittlement of ferrite matrix by the formation of additional phases such as G-phase, Type X, or the ..cap alpha..' phase. Carbide precipitation has a significant effect on the onset of embrittlement of CF-8 and -8M grades of stainless steels aged at 400 or 450/sup 0/C. The existing correlations do not accurately represent the embrittlement behavior over the temperature range 300 to 450/sup 0/C. 18 refs., 13 figs.
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab., IL (USA)
- OSTI Identifier:
- 6408052
- Report Number(s):
- CONF-8510173-25
ON: TI86003068
- DOE Contract Number:
- W-31-109-ENG-38
- Resource Type:
- Conference
- Resource Relation:
- Conference: 13. water reactor safety research information meeting, Gaithersburg, MD, USA, 22 Oct 1985
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; REACTOR MATERIALS; PWR TYPE REACTORS; EMBRITTLEMENT; PHYSICAL RADIATION EFFECTS; STAINLESS STEELS; CHARPY TEST; GRAIN BOUNDARIES; HIGH TEMPERATURE; MATHEMATICAL MODELS; MECHANICAL PROPERTIES; PRECIPITATION; REACTOR OPERATION; REACTOR SAFETY; ALLOYS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DESTRUCTIVE TESTING; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MATERIALS TESTING; MECHANICAL TESTS; MICROSTRUCTURE; OPERATION; RADIATION EFFECTS; REACTORS; SAFETY; SEPARATION PROCESSES; STEELS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS; 360106* - Metals & Alloys- Radiation Effects; 360103 - Metals & Alloys- Mechanical Properties; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
Citation Formats
Chopra, O K, and Chung, H M. Aging degradation of cast stainless steel. United States: N. p., 1985.
Web.
Chopra, O K, & Chung, H M. Aging degradation of cast stainless steel. United States.
Chopra, O K, and Chung, H M. 1985.
"Aging degradation of cast stainless steel". United States. https://www.osti.gov/servlets/purl/6408052.
@article{osti_6408052,
title = {Aging degradation of cast stainless steel},
author = {Chopra, O K and Chung, H M},
abstractNote = {A program is being conducted to investigate the significance of in-service embrittlement of cast-duplex stainless steels under light-water reactor operating conditions. Data from room-temperature Charpy-impact tests for several heats of cast stainless steel aged up to 10,000 h at 350, 400, and 450/sup 0/C are presented and compared with results from other studies. Microstructures of cast-duplex stainless steels subjected to long-term aging either in the laboratory or in reactor service have been characterized. The results indicate that at least two processes contribute to the low-temperature embrittleent of duplex stainless steels, viz., weakening of the ferrite/austenite phase boundary by carbide precipitation and embrittlement of ferrite matrix by the formation of additional phases such as G-phase, Type X, or the ..cap alpha..' phase. Carbide precipitation has a significant effect on the onset of embrittlement of CF-8 and -8M grades of stainless steels aged at 400 or 450/sup 0/C. The existing correlations do not accurately represent the embrittlement behavior over the temperature range 300 to 450/sup 0/C. 18 refs., 13 figs.},
doi = {},
url = {https://www.osti.gov/biblio/6408052},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Oct 01 00:00:00 EDT 1985},
month = {Tue Oct 01 00:00:00 EDT 1985}
}