The Thermal Scattering Law Project

Harnessing modern methods for material modeling and high-fidelity thermal scattering evaluations, the Scattering Law Project provides access to nuclear thermal scattering data from fundamental inputs to benchmark testing on key reactor and nuclear criticality materials to inspire and support the next generation of nuclear applications.

Uranium Nitride (UN)

Uranium nitride (UN) is a potential advanced reactor fuel material given its high density of uranium and improved thermal conductivity over UO2. UN was modelled using ab initio lattice dynamics (AILD) methods using the VASP and PHONON codes with the thermal scattering law (TSL) calculated using FLASSH 1.0. The data files generated for UN are generated for U-235 enrichments of 5%, 10% (LEU+), 19.75% (HALEU), 93% (HEU), 100%, and natural, representing the range of fuel enrichments applied for UN fuel.  

 

Publications

Impact of magnetic structure and thermal effects on vibrational excitations and neutron scattering in uranium mononitride

 

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