NSUF 15-591: Characterize Neutron Irradiated NF709 Stainless Steel Using Atom Probe Tomography
Austenitic stainless steel NF709 has been identified as one of the candidate structural materials for sodium-cooled fast reactors. However, the understanding on its irradiation response is very limited to date. Our preliminary results using high energy X-ray diffraction and TEM/STEM/EDS characterization show that the irradiation can induce a significant precipitate evolution in this alloy via dissolving the pre-existing Nb(C, N) precipitates and promoting new types of Ti/Cu enriched solute clusters. To fully understand irradiation effects on this alloy, it is proposed to further characterize the irradiated microstructure using APT by taking advantages of its exceptional elemental and spatial resolutions for chemical analysis. The completion of this study shall provide an unprecedented understanding on the fundamental mechanism of how the irradiation induced microstructural evolutions in this candidate alloy, and how they subsequently affect the material mechanical behavior under a thermal-mechanical loading which is currently under investigation through an ongoing NEET project.
Additional Info
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Abstract | Austenitic stainless steel NF709 has been identified as one of the candidate structural materials for sodium-cooled fast reactors. However, the understanding on its irradiation response is very limited to date. Our preliminary results using high energy X-ray diffraction and TEM/STEM/EDS characterization show that the irradiation can induce a significant precipitate evolution in this alloy via dissolving the pre-existing Nb(C, N) precipitates and promoting new types of Ti/Cu enriched solute clusters. To fully understand irradiation effects on this alloy, it is proposed to further characterize the irradiated microstructure using APT by taking advantages of its exceptional elemental and spatial resolutions for chemical analysis. The completion of this study shall provide an unprecedented understanding on the fundamental mechanism of how the irradiation induced microstructural evolutions in this candidate alloy, and how they subsequently affect the material mechanical behavior under a thermal-mechanical loading which is currently under investigation through an ongoing NEET project. |
Award Announced Date | 2015-08-10T00:00:00 |
Awarded Institution | None |
Facility | None |
Facility Tech Lead | Yaqiao Wu |
Irradiation Facility | None |
PI | Yong Yang |
PI Email | [email protected] |
Project Type | RTE |
RTE Number | 591 |