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- W2972212963 abstract "As fission fragments pass through UO2 nuclear fuel, a considerable concentration of Frenkel pair defects (i.e. vacancies and interstitials) are created. The steady-state concentration of these defects leads to enhanced uranium self-diffusion, one of several fundamental kinetic parameters that control key engineering properties such as creep and fission gas swelling in UO2 nuclear fuel. A cluster dynamics method to track point defects and defect clusters has been implemented in the MARMOT phase-field code in order to predict as-measured out-of-pile and irradiation enhanced thermal diffusivity. The calculated uranium self-diffusion coefficient compares well with non-irradiated fuel measurements, and shows similar trends to those observed in irradiated fuel, which is a good result given the complexities introduced by non-stoichiometric compositions." @default.
- W2972212963 created "2019-09-12" @default.
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- W2972212963 date "2019-12-01" @default.
- W2972212963 modified "2023-10-12" @default.
- W2972212963 title "Cluster dynamics simulation of uranium self-diffusion during irradiation in UO2" @default.
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- W2972212963 doi "https://doi.org/10.1016/j.jnucmat.2019.151787" @default.
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