NSUF 20-2958: Pulsed Neutron Characterization of U-1Pd-10Zr Irradiated Fuel
This project seeks support for beam scientist time at the Lujan Center to perform several pulsed neutron characterization techniques on U-1Pd-10Zr irradiated fuel for the first time. This alloy is under investigation to better understand if additives can be added to metallic nuclear fuel to improve performance by mitigating the effects of lanthanide fission product driven fuel cladding chemical interaction. Three dimensional neutron computed tomography will be used to investigate the pore structure and density variation of the irradiated fuel sample non-destructively and on a scale not possible with x-rays. Neutron resonance imaging will allow for the collection of spatially resolved elemental information. This will capture the radial distribution of Zr with more fidelity than has ever previously been possible. The location of Pd in the alloy will also be identified. At select locations the crystal structure phase of the irradiated material will be identified. This can provide valuable insights into the thermal history of the fuel and helps to better inform thermodynamic modeling of the U-Pd-Zr alloy system. All the tasks will be performed at the LANSCE Lujan center during the next beam cycle, June 2019 to December 2019. The sample is being shipped to Lujan independent of this award and will be ready to start immediately following an award. Data from this experiment is expected to support at least one if not several publications. Successful demonstration of this technique on irradiated fuel is also expected to create further demand for these techniques.
Additional Info
| Field | Value |
|---|---|
| Abstract | This project seeks support for beam scientist time at the Lujan Center to perform several pulsed neutron characterization techniques on U-1Pd-10Zr irradiated fuel for the first time. This alloy is under investigation to better understand if additives can be added to metallic nuclear fuel to improve performance by mitigating the effects of lanthanide fission product driven fuel cladding chemical interaction. Three dimensional neutron computed tomography will be used to investigate the pore structure and density variation of the irradiated fuel sample non-destructively and on a scale not possible with x-rays. Neutron resonance imaging will allow for the collection of spatially resolved elemental information. This will capture the radial distribution of Zr with more fidelity than has ever previously been possible. The location of Pd in the alloy will also be identified. At select locations the crystal structure phase of the irradiated material will be identified. This can provide valuable insights into the thermal history of the fuel and helps to better inform thermodynamic modeling of the U-Pd-Zr alloy system. All the tasks will be performed at the LANSCE Lujan center during the next beam cycle, June 2019 to December 2019. The sample is being shipped to Lujan independent of this award and will be ready to start immediately following an award. Data from this experiment is expected to support at least one if not several publications. Successful demonstration of this technique on irradiated fuel is also expected to create further demand for these techniques. |
| Award Announced Date | 2020-02-05T14:11:08.45 |
| Awarded Institution | Idaho National Laboratory |
| Facility | Advanced Test Reactor |
| Facility Tech Lead | Alina Zackrone, Tarik Saleh |
| Irradiation Facility | None |
| PI | Jason Harp |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 2958 |