This project seeks to address 1) pressure drop behavior of a typical sodium fast reactor fuel assembly with an orifice device and 2) orifice device onset of cavitation.
The objective of this project is to generate high-pedigree experimental data to help to validate the systems analysis codes SAS4A/SASSYS-1 and SAM which can be used to inform advanced reactor designers on thermal-hydraulic behavior during transients as well as support licensing activities.
The objective of this project was to use the thermal hydraulics laboratory and vacuum test chambers at Oak Ridge National Laboratory (ORNL) for response characterization of resistance temperature detectors and thermal aging of instrumentation and control (I&C) cables in vacuum to generate more useful data for I&C cable derating purposes.