About this Abstract |
Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
Presentation Title |
Wear and Friction Behavior of Fuel Pebbles in Molten Fluoride Salt |
Author(s) |
Gabriel Meric, Lorenzo Vergari, Jake Quincey, Raluca Scarlat, Terry Merriman, Micah Hackett |
On-Site Speaker (Planned) |
Lorenzo Vergari |
Abstract Scope |
Kairos Power’s fluoride-salt-cooled, high-temperature reactor (KP-FHR) technology uses a novel combination of existing technologies to achieve unique levels of economy, safety, flexibility, modularity and security for nuclear power production. The KP-FHR is a pebble-bed design that relies on TRISO fuel particles embedded in a graphite-like pebble as a fuel form. During online refueling and operation, fuel pebbles are continuously circulating through pebble handling systems and the core. Characterizing the friction and wear behavior of pebbles as they roll and slide against structural component surfaces and against each other is important for accurate modeling of the core behavior and to predict pebble wear and wear dust production. This talk will present tribology data and microstructural characterization for graphite sliding against 316H stainless steel and graphite in inert gas and in molten fluoride salt. The results exhibit the lubrication effect of fluoride salts. |
Proceedings Inclusion? |
Undecided |