Tech for use in Advanced Reactors vs. Existing Fleet
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 is to couple Serpent and Griffin to enable a thermal-hydraulics and neutronics multiphysics model of the transient scenario which will accelerate Radiant’s reactor design process.
Microreactor Control Drum Failure Simulation, Radiant Read More »
Westinghouse and Oak Ridge National Laboratory will use multiphysics design optimization methods and additive manufacturing to help develop new nuclear components as well as optimized replacements to existing components that are optimum for meeting design requirements and are manufacturable.
The objective of this project is to explore a number of advanced heterogenous fuel design concepts to improve the operational, safety, and economic performance of existing power plants.
Advanced Nuclear Fuel Pellet Designs, Exelon Nuclear Read More »
The objective of this project is to determine the density of actinidemolten salt solutions using neutron dilatometry.
The objective of this project is to assess the RELAP5- 3D code for application to the MSRR design and licensing pathway to resolve data limitations for both the input models for the plant design and models specific to the liquid fuel molten salt core.
The objective of this project is to use Large Eddy Simulations (LES) to produce numerical benchmark data that captures local velocity and temperature effects, and this data will have an immediate impact to accelerate technology development, enable economic optimization, and reduce regulatory uncertainty.
The objective of this project was to exact high quality, traceable data that quantifies composition dependencies and measurement uncertainty to inform operating conditions, which is paramount for proper design in any reactor, especially a liquid-fueled molten salt reactor.
Thermophysical Properties Measurements of NaCl-PuCl3, TerraPower LLC. Read More »
The benchmarks, analytical solutions, and failure criteria developed during this project will be used directly by USNC-Tech to evaluate the current graphite core design of the MMR™ reactor, resulting in an optimized core and a down-selection of the graphite used for the core.
Graphite Finite Element Model Verification, Ultra Safe Nuclear Corporation Read More »
To broaden the understanding of fuel-clad chemical interactions (FCCI), Oklo partnered with Idaho National Laboratory (INL) to conduct an out-of-pile experimental investigation into FCCI behavior that addresses each of these variables in order to expand the operating envelopes to better align with the Aurora reactor as well as other advanced concepts.
Addressing Gaps in Legacy Data on Fuel Steel Interactions, Oklo, Inc. Read More »
