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Morgan, Dane

Publications and source records attributed to Morgan, Dane.

151 records · Page 9
All sourcesNASA NTRSDOE OSTI
DOE OSTI2013

Spatially Resolved Mapping of Oxygen Reduction/evolution Reaction on Solid-Oxide Fuel Cell Cathodes with sub-10 nm Resolution

Spatial localization of the oxygen reduction/evolution reactions (ORR/OER) on lanthanum strontium cobaltite (LSCO) surfaces with perovskite and layered perovskite structures is studied on the sub-10 nanometer level. Comparison between Electrochemical Strain Microscopy (ESM) and structural imaging by scanning transmission electron microscopy (STEM) suggest that small-angle grain boundaries act as regions with enhanced electrochemical activity. The ESM activity is compared across a family of LSCO samples, demonstrating excellent agreement with macroscopic behaviors. This study potentially paves the way for deciphering the mechanisms of electrochemical activity of solids on the level of single extended structural defects such as grain boundaries and dislocations.

Electrochemical Strain microcsopy↗
DOE OSTI2012

Modeling Deep Burn TRISO Particle Nuclear Fuel

Under the DOE Deep Burn program TRISO fuel is being investigated as a fuel form for consuming plutonium and minor actinides, and for greater efficiency in uranium utilization. The result will thus be to drive TRISO particulate fuel to very high burn-ups. In the current effort the various phenomena in the TRISO particle are being modeled using a variety of techniques. The chemical behavior is being treated utilizing thermochemical analysis to identify phase formation/transformation and chemical activities in the particle, including kernel migration. First principles calculations are being used to investigate the critical issue of fission product palladium attack on the SiC coating layer. Density functional theory is being used to understand fission product diffusion within the plutonia oxide kernel. Kinetic Monte Carlo techniques are shedding light on transport of fission products, most notably silver, through the carbon and SiC coating layers. The diffusion of fission products through an alternative coating layer, ZrC, is being assessed via DFT methods. Finally, a multiscale approach is being used to understand thermal transport, including the effect of radiation damage induced defects, in a model SiC material.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗