| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Enabling In-situ Crack Growth Testing and Monitoring in VTR Cartridge Loop Environments |
| Author(s) |
Samuel A. Briggs, Peter Beck, Dustin Mangus, Jake Quincey, Andrew Brittan, George Young, Guillaume Mignot, Julie Tucker |
| On-Site Speaker (Planned) |
Samuel A. Briggs |
| Abstract Scope |
The Versatile Test Reactor (VTR) is a fast spectrum test reactor currently being developed in the United States under the direction of the US Department of Energy, Office of Nuclear Energy. While the conceptual design is a 300 MWth sodium-cooled fast reactor, it also incorporates self-contained cartridge loops, enabling experimentation in other advanced reactor coolant environments, including molten salts, gases, and other liquid metals. Oregon State University is supporting this program by developing techniques enabling instrumented, in-situ environmentally-assisted cracking (EAC) studies in various cartridge loop environments. To date, test facilities capable of fracture mechanics-based EAC testing in liquid sodium, molten salt, and supercritical CO2 environments have been developed. Additionally, commercially available non-destructive testing techniques, including potential drop and acoustic emission monitoring, are being adapted for use in the extreme coolant and radiation environments typified by VTR cartridge loops. A general overview of these efforts and initial results will be presented. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Environmental Effects, Mechanical Properties |