Thermal conductivity of SIMFUEL
- 1 June 1992
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 188, 198-204
- https://doi.org/10.1016/0022-3115(92)90471-v
Abstract
No abstract availableKeywords
This publication has 12 references indexed in Scilit:
- Formation and behaviour of barium silicate in UO2-based SIMFUELJournal of Nuclear Materials, 1991
- Microstructural features of SIMFUEL — Simulated high-burnup UO2-based nuclear fuelJournal of Nuclear Materials, 1991
- Thermal diffusivity of UO2-Gd2O3 pelletsJournal of Nuclear Materials, 1990
- A recommendation for the thermal conductivity of UO2Journal of Nuclear Materials, 1989
- Thermal conductivity of near-stoichiometric (U, Nd)O2, (U, Sm)O2 and (U, Eu)O2 solid solutionsJournal of Nuclear Materials, 1983
- Thermal conductivity of solid UO2: Critique and recommendationJournal of Nuclear Materials, 1983
- A re-appraisal of the thermal conductivity of UO2 and mixed (U, Pu) oxide fuelsJournal of Nuclear Materials, 1982
- The effect of gadolinium content on the thermal conductivity of near-stoichiometric (U,Gd)O2 solid solutionsJournal of Nuclear Materials, 1982
- The effect of yttrium content on the thermal conductivity of near-stoichiometric (U,Y)O2 solid solutionsJournal of Nuclear Materials, 1981
- High-Temperature Heat Contents of Uranium, Uranium Dioxide and Uranium Trioxide1Journal of the American Chemical Society, 1947