|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
||Mechanical Behavior of UO2 at Sub-Grain Length Scales: A Quantification of Creep Properties via High Temperature Mechanical Testing
||Benjamin Shaffer, Bowen Gong, Harn Chyi-Lim, Robert McDonald, Pedro Peralta
|On-Site Speaker (Planned)
Thermo-mechanical behavior of oxide nuclear fuels is critical to understand Pellet-Cladding Mechanical Interactions (PCMI) that can lead to fuel fracture, affecting fuel performance significantly. High temperature mechanical behavior, e.g. anisotropy of elastic properties as well as dislocation driven plasticity and creep, can also play a significant role on the mechanical behavior of fuels. This work investigates high temperature creep behavior using ex-situ mechanical testing of depleted Uranium Oxide (d-UO2) samples, heat-treated to obtain large grain sizes and different oxygen stoichiometries. Uniaxial compression testing will be performed at high temperatures under controlled atmospheres to ensure stoichiometry control, and will allow the measurement of creep strain rates and provide data to assist in the correlation of stoichiometry, crystallography, and mechanical behavior of oxide fuels. Samples will be characterized using Scanning Electron Microscopy (SEM) and Electron Backscatter Diffraction (EBSD), and the measured creep behavior will be correlated to microstructurally explicit finite element simulations.
||Planned: A print-only volume