| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
N-36: Stress Distribution of Disk Geometry Under Three-point Bending Tests to Evaluate Mechanical Properties of Neutron-irradiated Tungsten for Future Fusion Devices |
| Author(s) |
Trevor Marchhart, Nathan Clark Reid, Lauren Garrison, Jean Paul Allain |
| On-Site Speaker (Planned) |
Trevor Marchhart |
| Abstract Scope |
Advanced tungsten alloys have shown promise in future nuclear fusion reactors as plasma-facing components. The High Flux Isotope Reactor at Oak Ridge National Laboratory is used to screen potential fusion materials by irradiating 3 mm diameter disks. A miniaturized three-point bend test has been developed to test the mechanical properties of these neutron-irradiated disks. Three-point bend tests create both bending stress and shear stress within a sample, the amount of which is a function of the span-thickness ratio of the sample geometry. A finite element analysis simulation of the experimental set-up using ANSYS was conducted in order to understand the internal stress state of the materials during the three-point bend test and the influence of the sample thickness from 0.1 to 1 mm. The model was validated with experimental results and gives additional insight beyond what can be experimentally measured during the tests. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Modeling and Simulation |