Advanced Nuclear Reactor Coolants, Structural Materials, and Thermal Systems
This community focuses on the engineering of advanced nuclear reactors, specifically those using liquid coolants like molten salts and lead-bismuth eutectics, and the development of structural materials that can withstand the resulting corrosion and heat transfer challenges.
The research centers on the thermophysical properties of molten salts and liquid metals, with a heavy emphasis on corrosion behavior and heat transfer mechanisms in stainless steels and superalloys. Key topics include the design of fast reactors and small modular reactors, the analysis of fuel assemblies and spent fuel, and the application of Monte Carlo simulations for neutron transport. The work also addresses the electrochemical processing of nuclear materials and the integration of these systems for nuclear power generation, frequently examining the interaction between coolant chemistry and structural integrity over time.
This work represents a significant portion of research tracked for Plutonium (9.3%), Thorium (4.8%), and Uranium (4.4%). It also contributes a substantial share of the research output for Bismuth (2.3%), Lead (1.0%), and Sodium (1.0%).
The community comprises 39,517 papers, with the highest publication volumes in the Annals of Nuclear Energy, Nuclear Engineering and Design, and the Journal of Nuclear Science and Technology.
Recent work continues to focus on the corrosion of advanced alloys in lead-bismuth eutectic and molten salt environments, the development of nuclear data libraries, and the thermal-hydraulic analysis of fuel bundles. There is also ongoing research into the application of molten salts for thermal energy storage and industrial heat decarbonization.