Tam Fortis needs to validate its computational reactor design before finalizing a configuration for its planned zero-power criticality test. The company requires independent analysis to confirm criticality, shutdown margins, temperature feedback, power distribution, neutron leakage, and the interaction of the reactor’s neutronics, heat pipes, and hydride moderator.
BNNT Materials is developing BNNT-based gaskets for molten salt reactor systems, where high temperatures and corrosive salts create significant sealing challenges. The company needs specialized testing to demonstrate that its gaskets can withstand molten fluoride and chloride salts while maintaining sealing performance, chemical stability, and durability under reactor-relevant conditions.
Validation of BNNT Gaskets for High-Temperature Molten Salt Nuclear Systems Read More »
NuCube proposes to partner with Argonne National Laboratory (ANL) to verify an autonomous control architecture using a Digital Twin of the DeccaCell reactor. ANL will adapt its existing autonomous operation and diagnostics framework to demonstrate automated startup, remote monitoring, islanding-mode transitions, and predictive maintenance within a validated simulation environment. The project will generate a technically defensible basis for reduced staffing models and support future DOE and NRC licensing engagement.
Verification of Autonomous Operation and Remote Monitoring Capabilities Read More »
Zeno will partner with Argonne National Laboratory (ANL) to demonstrate the capabilities of a pyro-aqueous hybrid strontium separation process to provide technical data for Zeno to explore scale up in support of Zeno’s RPS designs. ANL’s Chemical and Fuel Cycle Technologies (CFCT) division have extensive experience in developing separation technologies for UNF recycling, in addition to medical isotope separation and purification. This project will generate successful flowsheet development to reduce the volume, heat load, and cost for UNF.
Recycling Nuclear Waste into a Strategic Asset Read More »
TerraPower will partner with Argonne National Laboratory (ANL) to generate NQA-1 qualifiable and traceable thermophysical property data for Beginning of Life (BOL) and simulated End of Life (EOL) ternary fuel salts. ANL has proven expertise in molten salt thermophysical measurement under NQA-1 standards. These results will directly inform reactor and component design, thermal hydraulic modeling, safety margines, and licensing strategies.
Thermophysical Property Measurements of NaCl-KCl-UCl3 Read More »
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 »
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 »
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).
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.
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 »
