| About this Symposium |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications III
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| Sponsorship |
TMS Structural Materials Division
TMS: Nuclear Materials Committee
TMS: Composite Materials Committee
TMS: Mechanical Behavior of Materials Committee
TMS: Advanced Characterization, Testing, and Simulation Committee
|
| Organizer(s) |
Anne A. Campbell, Oak Ridge National Laboratory
Dong (Lilly) Liu, University of Oxford
Rick Ubic, Boise State University
Lauren M. Garrison, Commonwealth Fusion Systems
Peng Xu, Idaho National Laboratory
Johann Riesch, Max-Planck-Insitut Fuer Plasmaphysik
James Wade-Zhu, University of Birmingham |
| Scope |
Composite materials are of growing interest for nuclear fusion and fission due to their combined excellent physical and mechanical properties that are compatible with extreme radiation and high temperature environments. With the development of next-generation fission reactors and fusion power, materials that can withstand higher neutron flux/thermal load/thermal mechanical stresses and more aggressive environments in terms of oxidation, corrosion/erosion, and tolerance to transmutation elements are required. This requirement makes it necessary to (i) understand the operational limits and degradation mechanisms of existing composite materials and (ii) develop and qualify new materials designs. There is a strong overlap in materials research between fission and fusion in terms materials design, processing, characterization, and modelling. This symposium aims to bring scientists and engineers together to share ideas and so join the effort in both fields at an international level for the development of these crucial composite materials and to enable collaborations across groups and countries. The design/processing/modelling/joining of the following materials, as well as their physical/mechanical characterization using ex situ and/or in situ techniques, are encouraged:
* Design, processing, and joining of composites for advanced fission and fusion reactors
* Modeling over multiple length scales
* Material physical and mechanical properties characterization using ex-situ and in-situ techniques
* Irradiation effects on materials properties and performance
* Chemical compatability reactor relevant environments
* Hydrogen transport and trapping
* Composite materials systems can include (but are not limited to):
* Graphite/carbon-based composites
* Ceramic-based composites
* Metal-matrix composites
* Composite nuclear fuels and claddings |
| Abstracts Due |
07/15/2024 |
| Proceedings Plan |
Planned: |