|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Corrosion in Heavy Liquid Metals for Energy Systems
||In-situ Crack Growth Testing in a Liquid Metal Environments
||Dustin Mangus, Peter Beck, Seth Walton, Guillaume Mignot, Wade Marcum, Julie Tucker, Samuel Briggs
|On-Site Speaker (Planned)
The U.S. Department of Energy (DOE) Versatile Test Reactor (VTR) program is attempting to address the capability gap in testing of advanced core materials, fuels, and instrumentation in prototypical environments proposed for next generation of nuclear reactors. The current VTR design concepts are based on the proven experience of pool-type, sodium-cooled reactors while adding integrated cartridge loops capable of housing other advanced reactor coolant environments (e.g., molten salts, Pb-Bi, etc). Oregon State University (OSU) is performing work in support of this program to enable in-situ mechanical testing in liquid metal and other advanced coolant environments. This work assesses the viability of using Direct Current Potential Drop (DCPD) and Alternating Current Potential Drop (ACPD) techniques to measure crack propagation in liquid metal coolants. Experimental testing and analytical models have been employed to determine whether their high electrical conductivity prevents these techniques from achieving the sensitivity necessary to monitor crack growth in-situ.
||Nuclear Materials, Mechanical Properties, Modeling and Simulation