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 Carbide (UC)

Uranium carbide (UC) is a nuclear fuel material which offers better neutron economy and lower fuel-cycle costs compared to conventional mixed-oxide fuels. UC 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 UC 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 UC fuel.   

 

Publications

Ab Initio Evaluation of Uranium Carbide S(α,β) and Thermal Neutron Cross Sections

 

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