| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification of Nuclear Materials Integrating Experiments, Modeling, and Theories
|
| Presentation Title |
High Temperature Ring-pull Mechanical Tests of Thin-walled Tube |
| Author(s) |
Benjamin P. Eftink, Peter Beck, Mathew Hayne, Tyler Dabney, Carl Cady, Tarik Saleh |
| On-Site Speaker (Planned) |
Benjamin P. Eftink |
| Abstract Scope |
Nuclear reactor environments impose high temperatures on in-core components. Depending on the reactor type, coatings on thin-walled cladding tubes may be used to mitigate oxidation during a loss of coolant accident or as a diffusion barrier to prevent materials degradation. Understanding the claddings mechanical behavior and the coatings adhesion at elevated temperatures is an important consideration for performance. For pressurized thin-walled tubes, such as cladding, the hoop direction observes the highest stresses and should be the direction tested. This talk will go through high temperature ring-pull tests to evaluate hoop direction mechanical properties and coating adhesion of nuclear fuel cladding thin-walled tube at elevated temperatures. These tests require only small segments of tube and can help evaluate materials concepts for high temperature environments. Nuclear reactor relevant materials were tested and will be discussed in terms of strength, ductility, and coating adherence at elevated temperatures. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Mechanical Properties, Nuclear Materials, |