| About this Abstract |
| Meeting |
Materials Science & Technology 2020
|
| Symposium
|
Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments
|
| 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 proposed fast-spectrum research reactor being developed by the U.S. Department of Energy to aid in design and licensing of next-generation nuclear reactors. While the primary coolant will be liquid sodium, the proposed design incorporates self-contained cartridge loops, enabling experimentation in other advanced reactor coolant environments, such as molten salts, gases, or other liquid metals. Efforts at Oregon State University are focused on developing techniques enabling fully-instrumented in-situ environmentally-assisted cracking (EAC) experiments in various cartridge loop environments. To date, EAC test facilities capable of corrosion fatigue, stress corrosion cracking, and liquid metal embrittlement studies in liquid sodium, molten salt, and supercritical CO2 environments have been developed. In addition, various non-destructive testing techniques, including potential drop and acoustic emission monitoring, are being adapted for use in cartridge loop environments and geometries. A general overview of these efforts and initial results will be presented. |