The objective of this project is to understand heat transfer for the novel molten fuel salt pin in a molten salt core concept. Heat transfer due to natural convection driven flow is a very complex phenomenon owing to the range of active length scales.
Salt to Metal to Salt Heat Transfer in Narrow Fuel Pins Read More »
This project will support the qualification of ARC’s fuel, by demonstrating the potential use of a barrier on the cladding to prevent fuel cladding chemical interaction (FCCI).
Development of Cladding Protective coating for FOAK ARC-100 Facility Read More »
The ARC Reactor is a thermal spectrum molten salt microreactor that uses low-enriched uranium fuel and operates at the high temperature of 600°C. Alpha Tech has identified YH2-x as an exceptional moderator that experiences little to no swelling.
Advanced Moderator Module Validation for the Alpha Tech Micro Molten Salt Reactor Read More »
This project seeks to model and experimentally confirm the composition of two known salt systems (LiF-NaF-UF4 and LiF-NaF-ThF4) as the fuel and blanket salt for Flibe’s Lithium Fluoride Low-Enrichment Uranium Reactor (LFLEUR).
Thermal Property Measurements for an LEU-Fueled Molten Salt Reactor, Flibe Energy, Inc. Read More »
The objective of this project was to test the Enduray Vision System developed by Vega Wave Systems Inc., using 3 MeV X-rays generated by the Van de Graaff system, to assess the radiation tolerance of the system. These tests showed that the Enduray Vision System was 10× more radiation-hard than the best available commercial competitor in terms of dose rate and can easily sustain radiation dose rates and total doses seen in the most extreme commercial applications in the nuclear energy industry.
Radiation Testing for Nuclear Inspection Systems, Vega Wave Systems Read More »
Oklo Inc. (Oklo) partnered with Argonne National Laboratory to accelerate the development of open-source and modern simulation tools. The project has an industry-wide impact since it advances the state-of-art simulation to design and build advanced reactor systems.
The objective of this project was to confirm the design and safety basis of Transatomic Power’s system by determining the thermophysical properties of the fuel salt proposed for use in the system.
Fuel Salt Characterization, Transatomic Power Corp. Read More »
The objective of this project was to convert spent nuclear fuel into molten-chloride-salt fuel and was intended to demonstrate the streamlined development of fuel salt manufacturing from spent nuclear fuel.
The objective of this project was to develop a computational capability for predicting radionuclide release from a broad spectrum of accidents that can be postulated to occur at liquid-metal-cooled reactor (LMR) facilities.
Argonne National Laboratory (ANL), Idaho National Laboratory (INL), and Kairos Power, LLC partnered to implement a multiscale thermal-fluids hierarchy analysis methodology for Kairos’ fluoride high-temperature reactor (FHR). The project demonstrated Kairos Power’s design optimization process for the heat exchanger, a vital component of the reactor’s design.
