Thermodynamic calculations of oxygen self-diffusion in mixed-oxide nuclear fuels
Research output: Contribution to journal › Article › peer-review
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DOI
Mixed-oxide fuels containing uranium with thorium and/or plutonium may play an important part in future nuclear fuel cycles. There are, however, significantly less data available for these materials than conventional uranium dioxide fuel. In the present study, we employ molecular dynamics calculations to simulate the elastic properties and thermal expansivity of a range of mixed oxide compositions. These are then used to support equations of state and oxygen self-diffusion models to provide a self-consistent prediction of the behaviour of these mixed oxide fuels at arbitrary compositions.
| Original language | Unknown |
|---|---|
| Pages (from-to) | 74018-74027 |
| Number of pages | 10 |
| Journal | RSC Advances |
| Volume | 6 |
| Issue number | 78 |
| DOIs | |
| Publication status | Published - 29 Jul 2016 |
| Externally published | Yes |