|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Characterization of U-10Mo fuel exposed to intermediate temperature irradiation conditions at the High Flux Isotope Reactor
||Peter Doyle, Jason Harp, Dylan Richardson, Tash Ulrich, Ian Greenquist, Andrew Nelson, Rachel Seibert, Grant Helmreich, Randy Fielding, Caleb Massey
|On-Site Speaker (Planned)
Metallic uranium alloys have been explored since the beginning of nuclear power due to their high uranium density and thermal conductivity. U-10Mo has been of specific interest because with 10 weight % Mo, the γ-U crystal structure is indefinitely stabilized in reactor service. Historically, radiation data on U-10Mo fuels has been collected in fast reactor or lower temperature research reactor conditions. This work will use the MiniFuel device at the High Flux Isotope Reactor at Oak Ridge National Laboratory to explore radiation effects in U-10Mo fuel samples exposed at intermediate temperatures not previously investigated. Test conditions are targeted at four temperatures between 250 and 500 ℃ and 3 target burnup conditions, up to 3.5%FIMA. After the reactor experiment, samples will be examined for fission gas release, swelling, and microstructural changes. Comparison of this data to pre-irradiation examinations will provide insight into the suitability of U-10Mo fuels for broader applications.
||Characterization, Nuclear Materials, Other