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.
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.
The objective of this project is to quantify the economic advantages of burning spent nuclear fuel (SNF) from light water reactors (LWRs) in a GEM*STAR accelerator-driven subcritical reactor.
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.
The objective of this project was to determine the design feasibility of Micro Nuclear LLC’s Molten Salt Nuclear Battery (MsNB) by performing computational analysis and discussing the likely multiphysics modeling challenges while coupling thermal hydraulics and neutronics.
The objective of this project was to explore the applicability of Power Fluidics™ (PF) to molten salt systems and to determine if PF technology may be able to fulfill some of the forced-flow testing required in support of MSR R&D.
The objective of this project was to focus on the coupling of three high fidelity analysis codes for detailed core analysis, an analysis of the Oklo reactor design to assesses the potential for radionuclide release to the environment during accident scenarios, and an assessment and provision of relevant metal fuel data through inspection of post-irradiation examination data from past metal fuel testing. This project had two additional objectives, the experimental characterization of liquid metal heat pipe performance, failure behavior, and phenomena and the testing of generic heat pipes beyond their design limits, providing original data and insights.
The objective of this project was to procure, prepare, and characterize fluoride salt compositions relevant to Terrestrial Energy USA, Inc.’s Integral Molten Salt Reactor (IMSR®) design. Then, the project set out to investigate the fuel salts’ thermal conductivities, viscosities, and densities.
The objective of this project was to review Columbia Basin Consulting Group (CBCG)’s design concept for a leadbismuth-cooled fast reactor and thereafter to determine how the design might benefit from the functional containment concept, which allows the designer to take credit for a sequence of barriers to contain or confine radionuclides.