Percolation model for bubble interlinkage in ceramic nuclear fuels
- 1 November 1983
- journal article
- other
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 119 (1) , 116-118
- https://doi.org/10.1016/0022-3115(83)90060-0
Abstract
No abstract availableKeywords
This publication has 8 references indexed in Scilit:
- GRABB—A Computer Code for Simulating Fission Gas Dispostion in Oxide Fuel During Fast Thermal TransientNuclear Technology, 1983
- Physical processes and mechanisms related to fission gas swelling in MX-type nuclear fuelsJournal of Nuclear Materials, 1979
- Swelling in UO2under conditions of gas releasePhilosophical Magazine, 1974
- A Note on Percolation ProbabilitiesPhysica Status Solidi (b), 1973
- The morphology and growth rate of interlinked porosity in irradiated UO2Journal of Nuclear Materials, 1973
- An introduction to percolation theoryAdvances in Physics, 1971
- Interpretations of Fission Gas Behavior in Refractory FuelsNuclear Applications and Technology, 1970
- Examination of neutron-irradiated UO2 using the scanning electron microscopeJournal of Materials Science, 1970