NSUF 13-432: Radiation resistance of novel ODS alloy
A novel Oxide Dispersion Strengthened (ODS) ferritic alloy was developed at the Center of Advanced Energy Studies. The novelty lies is the chemical composition of the nanoclusters, which are enriched in zirconium. This alloy had a Vickers hardness value of 630, significantly higher than sintered samples with Y-O and Y-O-Ti nanoclusters, which exhibited hardness values less than 500. In order to confirm that this material is a promising candidate for nuclear application, it is necessary to prove that these oxide particles remain stable under irradiation. A fast and efficient method to estimate the stability of the nanoclusters under irradiation is to use heavy ions irradiation. Such irradiation can be conducted at the accelerator at the University of Michigan. This ATR NSUF partner facility offers 5MeV self ion irradiation capability with a good temperature control up to ~400ºC. Irradiation to high dose (150 dpa) will be conducted using 5 MeV Fe++ ions to minimize the change in composition of the near-surface region. Samples will be irradiated at 10-3 dpa/s to three doses: 50, 100 and 150 dpa at 400 ºC. Although a full characterization of the stability of the proposed nanocluster compositions would demand a larger range of temperature and dose, the condition chosen are believe to demonstrate the potential of such nanocluster while permitting comparison with literature data and be compatible with the current irradiation capability. Four heats of material will be irradiated: two ODS alloys created with the conventional Y-O and Y-O-Ti nanoclusters and the two novel ODS alloys with Y-O-Zr and Y-O-Ti-Zr nanoclusters. After irradiation, the samples will be sent back to CAES where the irradiated microstructure will be characterized. Evidence in changes in oxide size and density will be looked for. It is expected that the research will show that the Zr containing nanoclusters are as stable as the nanoclusters without Zr. Such result would prove that the novel ODS alloys, with improved mechanical properties, are promising candidates for nuclear applications. It is expected to be able to reach such conclusion by the end of fiscal year 2013.
Additional Info
| Field | Value |
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| Abstract | A novel Oxide Dispersion Strengthened (ODS) ferritic alloy was developed at the Center of Advanced Energy Studies. The novelty lies is the chemical composition of the nanoclusters, which are enriched in zirconium. This alloy had a Vickers hardness value of 630, significantly higher than sintered samples with Y-O and Y-O-Ti nanoclusters, which exhibited hardness values less than 500. In order to confirm that this material is a promising candidate for nuclear application, it is necessary to prove that these oxide particles remain stable under irradiation. A fast and efficient method to estimate the stability of the nanoclusters under irradiation is to use heavy ions irradiation. Such irradiation can be conducted at the accelerator at the University of Michigan. This ATR NSUF partner facility offers 5MeV self ion irradiation capability with a good temperature control up to ~400ºC. Irradiation to high dose (150 dpa) will be conducted using 5 MeV Fe++ ions to minimize the change in composition of the near-surface region. Samples will be irradiated at 10-3 dpa/s to three doses: 50, 100 and 150 dpa at 400 ºC. Although a full characterization of the stability of the proposed nanocluster compositions would demand a larger range of temperature and dose, the condition chosen are believe to demonstrate the potential of such nanocluster while permitting comparison with literature data and be compatible with the current irradiation capability. Four heats of material will be irradiated: two ODS alloys created with the conventional Y-O and Y-O-Ti nanoclusters and the two novel ODS alloys with Y-O-Zr and Y-O-Ti-Zr nanoclusters. After irradiation, the samples will be sent back to CAES where the irradiated microstructure will be characterized. Evidence in changes in oxide size and density will be looked for. It is expected that the research will show that the Zr containing nanoclusters are as stable as the nanoclusters without Zr. Such result would prove that the novel ODS alloys, with improved mechanical properties, are promising candidates for nuclear applications. It is expected to be able to reach such conclusion by the end of fiscal year 2013. |
| Award Announced Date | 2013-06-13T00:00:00 |
| Awarded Institution | Idaho National Laboratory |
| Facility | Advanced Test Reactor |
| Facility Tech Lead | Alina Zackrone, Kevin Field, Kory Linton, Stuart Maloy, Tarik Saleh |
| Irradiation Facility | None |
| PI | Sebastien Teysseyre |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 432 |