Modelling of UO2-based SIMFUEL thermal conductivity The effect of the burnup
- 1 December 1994
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 217 (3) , 279-286
- https://doi.org/10.1016/0022-3115(94)90377-8
Abstract
No abstract availableKeywords
This publication has 12 references indexed in Scilit:
- Fuel rod and core materials investigations related to LWR extended burnup operationJournal of Nuclear Materials, 1992
- Thermal conductivity of SIMFUELJournal of Nuclear Materials, 1992
- 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
- A recommendation for the thermal conductivity of UO2Journal of Nuclear Materials, 1989
- Theory of thermal conduction in dielectric solids: Effects of radiation damageNuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 1984
- 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 yttrium content on the thermal conductivity of near-stoichiometric (U,Y)O2 solid solutionsJournal of Nuclear Materials, 1981
- Thermal Resistance due to Point Defects at High TemperaturesPhysical Review B, 1960