Temperature measurements in high burnup UO2 nuclear fuel: Implications for thermal conductivity, grain growth and gas release
- 31 July 1994
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 211 (1) , 11-29
- https://doi.org/10.1016/0022-3115(94)90276-3
Abstract
No abstract availableKeywords
This publication has 17 references indexed in Scilit:
- Microstructural analysis of LWR spent fuels at high burnupPublished by Elsevier ,2003
- Observations of athermal gas release from water-reactor fuel at extended burnupJournal of Nuclear Materials, 1993
- Thermal conductivity of uranium dioxideJournal of Nuclear Materials, 1993
- Thermal conductivity of SIMFUELJournal of Nuclear Materials, 1992
- Concerning the microstructure changes that occur at the surface of UO2 pellets on irradiation to high burnupJournal of Nuclear Materials, 1992
- Development and characteristics of the rim region in high burnup UO2 fuel pelletsJournal of Nuclear Materials, 1992
- Comment on the diffusion of fission gas in UO2 during power transients at high burn-upJournal of Nuclear Materials, 1985
- Local fission gas release and swelling in water reactor fuel during slow power transientsJournal of Nuclear Materials, 1985
- Transiente spaltgasfreisetzung und UO2-mikrostruktur bei leistungsrampenJournal of Nuclear Materials, 1984
- Isothermal grain growth kinetics in sintered UO2 pelletsJournal of Nuclear Materials, 1973