Development of CAP process for fabrication of ThO2–UO2 fuels Part II: Characterization and property evaluation
- 15 February 2008
- journal article
- Published by Elsevier BV in Journal of Nuclear Materials
- Vol. 373 (1-3), 309-318
- https://doi.org/10.1016/j.jnucmat.2007.06.011
Abstract
No abstract availableKeywords
This publication has 27 references indexed in Scilit:
- Fission gas release in FBR MOX fuel irradiated to high burnupJournal of Nuclear Materials, 2005
- Modelling thermal conductivity and self-irradiation effects in mixed oxide fuelsJournal of Nuclear Materials, 2003
- Thermophysical properties of uranium dioxideJournal of Nuclear Materials, 2000
- Thermal conductivity of ThO2 and Th0.98U0.02O2Journal of Nuclear Materials, 2000
- Fission gas release during grain growth in a microstructure with a distribution of grain sizesJournal of Nuclear Materials, 1993
- High temperature X-ray diffractometric studies on the lattice thermal expansion behaviour of UO2, ThO2 and (U0.2Th0.8)O2 doped with fission product oxidesJournal of Nuclear Materials, 1991
- Model for the electronic contribution to the thermal and transport properties of ThO2, UO2, and PuO2 in the solid and liquid phasesJournal of Nuclear Materials, 1979
- The relation between microstructure and the release of unstable fission products during high temperature irradiation of uranium dioxideJournal of Nuclear Materials, 1978
- Thermal diffusivity of mixed (Th1−xUx) oxides and some materials to be used as reference in the range 650–2 700 KJournal of Nuclear Materials, 1972
- The porosity correction factor for the thermal conductivity of ceramic fuelsJournal of Nuclear Materials, 1971