Swelling in UO2under conditions of gas release
- 1 July 1974
- journal article
- research article
- Published by Taylor & Francis in Philosophical Magazine
- Vol. 30 (1), 47-63
- https://doi.org/10.1080/14786439808206532
Abstract
A model is developed to describe the kinetics of swelling in nuclear fuels during irradiation, when tunnels formed along grain edges by the coalescence of fission gas bubbles interlink with one another to form a network through which the entrained gas can escape to the surroundings. The predicted dependence of swelling on time, rating, external restraint pressure and temperature is physically acceptable and in qualitative agreement with existing observations.Keywords
This publication has 9 references indexed in Scilit:
- The effect of grain size on the swelling and gas release properties of uo2 during irradiationJournal of Nuclear Materials, 1974
- The morphology and growth rate of interlinked porosity in irradiated UO2Journal of Nuclear Materials, 1973
- The sintering of grain boundary cavities in uranium dioxideJournal of Nuclear Materials, 1972
- The effect of fission products on the ratio of grain-boundary energy to surface energy in irradiated uranium dioxideJournal of Nuclear Materials, 1971
- Examination of neutron-irradiated UO2 using the scanning electron microscopeJournal of Materials Science, 1970
- The growth of fission gas bubbles in irradiated uranium dioxidePhilosophical Magazine, 1969
- A study of cation diffusion in UO2 + x and ThO2 using α-ray spectrometryJournal of Nuclear Materials, 1968
- The surface self-diffusion of uranium dioxideJournal of Nuclear Materials, 1967
- Sintering Crystalline Solids. I. Intermediate and Final State Diffusion ModelsJournal of Applied Physics, 1961