Nuclear Fuel Materials and Reactor Performance Modeling
This community investigates the physical and chemical behavior of nuclear fuels and reactor components under irradiation, with a focus on thermal management, structural integrity, and the management of fission products.
The work centers on uranium dioxide, plutonium, and thorium-based materials, analyzing their thermal conductivity, phase transformations, and mechanical properties. Recurring methodologies include molecular dynamics, Monte Carlo simulations, and machine learning to model fuel assembly behavior, fission gas release, and severe accident scenarios. The research spans various reactor types, including pressurized water reactors, sodium-cooled fast reactors, and small modular reactors, often examining the implications for the fuel cycle and spent fuel management.
The largest share of the community's output is found in plutonium research, accounting for 15.2% of all plutonium research, and 5,584 papers here. Uranium research follows with 10.1% of its total output, representing 11,198 papers in this group.
This research community comprises 39,639 papers, primarily published in the Journal of Nuclear Materials, Nuclear Engineering and Design, and the Journal of Nuclear Science and Technology.
Recent work includes studies on high-temperature phase transformations in uranium-molybdenum-titanium-zirconium alloys, Raman spectroscopy applications in nuclear materials, and melting transition measurements in uranium dioxide.