Argonne National Laboratory (ANL) Archives

Candidate Materials Tribology Testing for Sodium Bearing in Sodium Fast Reactors

Hayward Tyler will partner with Argonne National Laboratory (ANL) to perform tribological (wear) testing of several candidate materials that offer superior wear resistance while reducing the radiological hazards of cobalt bearing materials. They also plan to test the bearings to ascertain surface wear mechanisms using the Mechanisms Engineering Test Loop (METL) facility. The benefits of this project will be to identify alternative bearing materials to decrease costs and enhance safety.

Candidate Materials Tribology Testing for Sodium Bearing in Sodium Fast Reactors Read More »

Salt to Metal to Salt Heat Transfer in Narrow Fuel Pins, Moltex Energy

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, Moltex Energy Read More »

Development of Cladding Protective coating for FOAK ARC-100 Facility, ARC Clean Technology

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, ARC Clean Technology Read More »

Advanced Moderator Module Validation for the Alpha Tech Micro Molten Salt Reactor, Alpha Tech Research Corp

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, Alpha Tech Research Corp Read More »

Thermal Property Measurements for an LEU-Fueled Molten Salt Reactor, Flibe Energy

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 Read More »

Radiation Testing for Nuclear Inspection Systems, Vega Wave Systems

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 »

Accelerate Development of Industry-Relevant Features in Modern Simulation tools, Oklo Inc.

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.

Accelerate Development of Industry-Relevant Features in Modern Simulation tools, Oklo Inc. Read More »

Fuel Salt Characterization, Transatomic Power Corp.

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 »

Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear fuel, Elysium Industries

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.

Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear fuel, Elysium Industries Read More »

Development of an Integrated Mechanistic Source Term Assessment Capability for Lead- and Sodium-Cooled Fast Reactors, Fauske & Associates LLC

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.

Development of an Integrated Mechanistic Source Term Assessment Capability for Lead- and Sodium-Cooled Fast Reactors, Fauske & Associates LLC Read More »