A microstructure-dependent model for fission product gas release and swelling in UO2 fuel
- 29 February 1980
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 56 (1) , 163-175
- https://doi.org/10.1016/0029-5493(80)90180-6
Abstract
No abstract availableKeywords
This publication has 8 references indexed in Scilit:
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- Irradiation-induced volume changes in commercial UO2 fuel: Comparison with model predictionJournal of Nuclear Materials, 1978
- Identification of precipitates associated with intergranular fission gas bubbles in irradiated UO2 fuelJournal of Nuclear Materials, 1976
- Swelling in UO2under conditions of gas releasePhilosophical Magazine, 1974
- The effect of grain size on the swelling and gas release properties of uo2 during irradiationJournal of Nuclear Materials, 1974
- Isothermal grain growth kinetics in sintered UO2 pelletsJournal of Nuclear Materials, 1973
- Thermal-gradient migration of helium bubbles in uranium dioxideJournal of Nuclear Materials, 1973
- An electron microscope examination of matrix fission-gas bubbles in irradiated uranium dioxideJournal of Nuclear Materials, 1971