|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Computational Materials Science and Engineering for Nuclear Energy
||Thermophysical Properties of (U,Zr)O2 Pellet-cladding Interface though MD Simulations
||Dillon Frost, Michael W D Cooper, Patrick A Burr
|On-Site Speaker (Planned)
The pellet-cladding interface of conventional UO2/Zr-alloy fuel is characterised by the presence of a solid solution (U,Zr)O2 phase, with thermophysical properties that are largely still unknown.
Using molecular dynamics, the thermophysical properties of the (U,Zr)O2 system have been investigated between 300 and 3600 K. Specifically, the thermal expansion coefficient, heat capacity, melting point, thermal conductivity and cubic-tetragonal transformation temperature were predicted for a range of Zr/U ratios. The results have been compared to those of (U,Th)O2 and (U,Pu)O2 solid solution, for which more ample investigations are available. The results may feed directly into meso- and macro-scale models and microstructure-based fuel performance codes.
||Planned: Supplemental Proceedings volume