| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications II
|
| Presentation Title |
Role and Structure of HTGR Matrix Material |
| Author(s) |
Tyler J. Gerczak, Anne A Campbell, Grant W Helmreich, William F Cureton, Elizabeth Sooby, Ryan Latta, Gerald E Jellison, John D Hunn |
| On-Site Speaker (Planned) |
Tyler J. Gerczak |
| Abstract Scope |
Typical fuel forms for high temperature gas-cooled reactors consist of tristructural isotopic (TRISO) coated particles dispersed within a composite matrix of graphite flake and partially carbonized resin binder. In general, the final fuel form is either a right cylindrical compact or spherical pebble. The matrix material provides multiple functions such as neutron moderation, control of inter-particle spacing, structural support, and mitigation of fission product release. The matrix has generally received less attention relative to the TRISO fuel particle. Here, a discussion on the matrix structure and its relationship to the overcoating and compacting process will be presented. Additional insight on the influence of microstructure on the matrix’s thermophysical properties and their impact on fuel performance during normal and transient operating conditions will be explored. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, |