|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Modeling of Fission Gas Behavior in Uranium Nitride Fuel
||Jason Rizk, Christopher Matthews, Michael Cooper, Anders David Andersson
|On-Site Speaker (Planned)
Uranium nitride fuel is a candidate for accident tolerant fuel designs and microreactors due to its high uranium density and high thermal conductivity. Its fission gas and swelling behaviors need to be better understood before its widespread use. Uranium nitride, like uranium carbide, exhibits “breakaway swelling,” which is an accelerated swelling rate once conditions exceed temperature and burnup thresholds. Free energy cluster dynamics simulations are used to calculate irradiation-enhanced Xe diffusion and track irradiation damage. The diffusion coefficients are utilized in fuel performance simulations to calculate fission gas release and swelling. The fuel performance simulations are compared to experimental results, and a sensitivity analysis and uncertainty quantification are performed. This work advances the fuel performance modeling capabilities of uranium nitride fuel, and provides insight into the “breakaway swelling” phenomenon.