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 »
The objective of this project was to analyze reactor core and system behavior in response to anticipated transients and accident scenarios and to use the Virtual Environment for Reactor Applications (VERA) code suite, which employs multi-physics simulation to model feedback behavior in the reactor core.
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 »
Neutroelectric and Oak Ridge National Laboratory will perform critical combined tests at the High Flux Isotope Reactor in support of qualification of this new material, NE-300, for use in commercial nuclear reactor applications.
The scope of this project included the design of an experiment for irradiating Lightbridge metallic fuel material samples in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL).
