FRACTURE RESISTANCE OF CAST AUSTENITIC STAINLESS STEELS
Cast austenitic stainless steels (CASS) possess excellent corrosion resistance and mechanical properties and are used alongside with wrought stainless steels (SS) in light water reactors for primary pressure boundaries and reactor core internal components. In contrast to an austenitic microstructure of wrought SS, CASS alloys consist of a dual-phase microstructure of delta ferrite and austenite. While the delta ferrite is critical for the service performance of CASS alloys, it is also vulnerable to embrittlement when exposed to reactor service temperatures and fast neutron irradiations. In this study, the combined effect of thermal aging and neutron irradiation on the degradation of CASS alloys was investigated. Static casts of CF-3 and CF-8 grades with > 23% delta ferrite were selected for the study, and specimens with and without prior thermal aging were irradiated at ~320°C to about 0.08 dpa. Crack growth rate and fracture toughness J-integral resistance curve tests were performed in simulated light water reactor environments with low corrosion potential. While no elevated crack propagation rates were detected, significant reductions in fracture toughness were observed after either thermal aging or neutron irradiation. The loss of fracture toughness due to neutron irradiation seemed more evident in the samples without prior thermal aging. Transmission electron microscope (TEM) examination showed that both neutron irradiation and thermal aging affect the microstructural evolution of delta ferrite. A high density of G-phase precipitates was observed in both thermally aged and irradiated specimens The evolution of the precipitate microstructure is more extensive in the samples subjected to both thermal aging and neutron irradiation. The similarity of precipitate microstructures resulting from thermal aging and neutron irradiation are consistent with the fracture toughness results, suggesting a common microstructural origin of the observed embrittlement among the tested specimens.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- U. S. Nuclear Regulatory Commission (NRC)
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1579524
- Resource Relation:
- Conference: 24th International Conference on Nuclear Engineering (ICONE 24), 06/26/16 - 06/30/16, Charlotte, NC, US
- Country of Publication:
- United States
- Language:
- English
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