Nuclear Fuel Materials and Reactor Performance Modeling
This community investigates the physical and chemical behavior of nuclear fuel materials under irradiation and high-temperature conditions to support reactor design and safety.
The work centers on uranium dioxide, uranium nitride, and mixed oxide fuels, analyzing how they respond to fission gas release, thermal conductivity changes, and structural degradation. Key methods include molecular dynamics simulations, density functional theory, and multiphysics modeling of fuel pellets and rods. The research addresses specific reactor types, including sodium-cooled fast reactors and research reactors, with a focus on fission product behavior, ion irradiation effects, and the development of metallic fuel forms.
Plutonium research is the largest share of this community's output, accounting for 9.2% of all plutonium research tracked, with 3,374 papers in this group. Uranium research follows with 7.4% of all uranium research, comprising 7,986 papers.
The community comprises 25,676 papers, publishing primarily in the Journal of Nuclear Materials, Journal of Nuclear Science and Technology, and Nuclear Engineering and Design.
Recent work continues to focus on phase transformations in uranium alloys, thermal transport in irradiated thorium dioxide, and molecular dynamics simulations of xenon-induced swelling in uranium-zirconium alloys.