| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments
|
| Presentation Title |
Environmental Induced Defects on the Microstructure of Nuclear Graphite |
| Author(s) |
David David Arregui-Mena, Jisue Moon, Cristian Contescu, Lianshan Lin, Nidia Gallego |
| On-Site Speaker (Planned) |
David David Arregui-Mena |
| Abstract Scope |
Graphite is a candidate material for moderating fast neutrons and as structural components in the US next-generation graphite-moderated reactors. A graphite core is conceived as a large formation of interconnected bricks that primarily moderates fast neutrons, holds instrumentation, fuel elements, control rods, and is a receptacle for molten salts for Molten Salt Reactors (MSRs) designs. During the operation of a graphite-moderated power plant, graphite components might experience oxidation, neutron-induced defects, fluorination, or other degradation mechanisms that modify the graphite microstructure. This talk will show the results of different characterization techniques applied to study the oxidation, graphite, and molten salt interactions as well as neutron irradiation effects in this material. Particular emphasis will be given to 3D characterization techniques used to study nuclear graphite's microstructure and degradation effects. This characterization is being conducted to understand the resilience of different graphite grades and to document the effects of degradation mechanisms in graphite. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Characterization, Nuclear Materials |