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Controlling low temperature sintering of UO2+x

dc.contributor.authorFrost, DGen_AU
dc.contributor.authorBurr, PAen_AU
dc.contributor.authorObbard, EGen_AU
dc.contributor.authorVeliscek-Carolan, Jen_AU
dc.date.accessioned2026-05-07T06:07:17Zen_AU
dc.date.issued2024-11en_AU
dc.date.statistics2025-04-02en_AU
dc.description.abstractUO2 nuclear fuel pellets are typically sintered at temperatures of approximately 1700 °C to achieve the high densities and large grain sizes necessary for safe reactor operation. Lowering this sintering temperature is desirable in order to decrease the energy input required for fuel manufacture. Hence, the effect of temperature, time, stoichiometry and ZrO2 doping on sintering efficacy have been investigated. ZrO2 doping, coupled with hyper-stochiometry, acted as a strong sintering aid, enabling higher densities and larger grain sizes when sintering at lower temperatures and for shorter periods compared to the undoped samples. Without ZrO2 doping, at 1500 °C sintering was strongly sensitive to hyper-stoichiometry and only weakly sensitive to sintering duration. Addition of 0.13 mol fraction ZrO2 increased theoretical density up to 10 % and the maximum grain size from 8 µm to 40 µm. Addition of 0.30 mol fraction ZrO2 resulted in even greater densification, reaching 98 % of maximum theoretical density, but also formation of a secondary phase that hindered grain growth. © 2024 Published by Elsevier B.V.en_AU
dc.identifier.articlenumber155269en_AU
dc.identifier.citationFrost, D. G., Burr, P. A., Obbard, E. G., & Veliscek-Carolan, J. (2024). Controlling low temperature sintering of UO2+x. Journal of Nuclear Materials, 600, 155269. doi:10.1016/j.jnucmat.2024.155269en_AU
dc.identifier.issn0022-3115en_AU
dc.identifier.journaltitleJournal of Nuclear Materialsen_AU
dc.identifier.urihttps://doi.org/10.1016/j.jnucmat.2024.155269en_AU
dc.identifier.urihttps://apo.ansto.gov.au/handle/10238/17210en_AU
dc.identifier.volume600en_AU
dc.languageEnglishen_AU
dc.language.isoenen_AU
dc.publisherElsevieren_AU
dc.subjectTemperature rangeen_AU
dc.subjectNuclear fuelsen_AU
dc.subjectReactor operationen_AU
dc.subjectStoichiometryen_AU
dc.subjectZirconiumen_AU
dc.subjectOxygenen_AU
dc.subjectSinteringen_AU
dc.subjectNuclear fuelsen_AU
dc.subjectDoped materialsen_AU
dc.subjectThermal conductivityen_AU
dc.subjectUraniumen_AU
dc.subjectDiffusionen_AU
dc.titleControlling low temperature sintering of UO2+xen_AU
dc.typeJournal Articleen_AU

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