Aging degradation of cast stainless steel
Description
A program is being conducted to investigate the significance of in-service embrittlement of cast duplex stainless steels under light-water reactor operating conditions. Microstructures of cast materials subjected to long-term aging either in reactor service or in the laboratory have been characterized by TEM, SANS, and APFIM techniques. Two precipitate phases, i.e., the Cr-rich α' and Ni- and Si-rich G phase, have been identified in the ferrite matrix of the aged steels. The results indicate that the low-temperature embrittlement is primarily caused by α' precipitates which form by spinodal decomposition. The relative contribution of G phase to loss of toughness is now known. Microstructural data also indicate that weakening of ferrite/austenite phase boundary by carbide precipitates has a significant effect on the onset and extent of embrittlement of the high-carbon CF-8 and CF-8M grades of stainless steels, particularly after aging at 400 or 4500C. Data from Charpy-impact, tensile, and J-R curve tests for several heats of cast stainless steel aged up to 10,000 h at 350, 400, and 4500C are presented and correlated with the microstructural results. Thermal aging of the steels results in an increase in tensile strength and a decrease in impact energy, J/sub IC/, and tearing modulus. The fracture toughness results show good agreement with the Charpy-impact data. The effects of compositional and metallurgical variables on loss of toughness are discussed
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01; 1 as DE87004939.Files
18065779.pdf
Files
(840.2 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:a91599273e25094113288cbb72292265
|
840.2 kB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 42 p.
- Report number
- CONF-8610135--59
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18065779
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; BWR TYPE REACTORS; EMBRITTLEMENT; MATERIALS TESTING; MECHANICAL PROPERTIES; MICROSTRUCTURE; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; REACTOR MATERIALS; RESEARCH PROGRAMS; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; POWER REACTORS; RADIATION EFFECTS; REACTORS; STEELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.