NSUF 23-4774: Quantification of local burnup in irradiated U-10Zr metallic fuel using Atom Probe Tomography
The objective of this study is to quantify the radial distribution of local burn up, main fuel elements (U, Zr) and fission products in a neutron irradiated U-10Zr metallic nuclear fuel. The main hypothesis we want to test is the possible presence of a radial gradient in burnup, and thus fission rate, across the pin radius, which may contribute, together with gradients in temperature, to the local evolution and redistribution of fuel (U-Zr) phases. We expect to perform the experimental work in a three weeks time frame, possibly in June 2023, while the data analysis and manuscript writing will take place between July and September 2023. The expected scientific outcome is a manuscript to be submitted to a relevant peer-reviewed journal such as the Journal of the American Ceramic Society, Acta Materialia, or the Journal of Nuclear Materials. If the research is successful, the acquired information will facilitate deeper understanding of the behavior of this fuel material under irradiation, providing input data for validation and development of modeling codes, such as BISON and MARMOT.
Additional Info
| Field | Value |
|---|---|
| Abstract | The objective of this study is to quantify the radial distribution of local burn up, main fuel elements (U, Zr) and fission products in a neutron irradiated U-10Zr metallic nuclear fuel. The main hypothesis we want to test is the possible presence of a radial gradient in burnup, and thus fission rate, across the pin radius, which may contribute, together with gradients in temperature, to the local evolution and redistribution of fuel (U-Zr) phases. We expect to perform the experimental work in a three weeks time frame, possibly in June 2023, while the data analysis and manuscript writing will take place between July and September 2023. The expected scientific outcome is a manuscript to be submitted to a relevant peer-reviewed journal such as the Journal of the American Ceramic Society, Acta Materialia, or the Journal of Nuclear Materials. If the research is successful, the acquired information will facilitate deeper understanding of the behavior of this fuel material under irradiation, providing input data for validation and development of modeling codes, such as BISON and MARMOT. |
| Award Announced Date | 2023-09-14T13:32:25.38 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Alina Zackrone |
| Irradiation Facility | None |
| PI | Daniele Salvato |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | None |