Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
9793657 | Journal of Nuclear Materials | 2005 | 7 Pages |
Abstract
Most nuclear fuel oxidation research has addressed either low-temperature (<700Â K) air oxidation related to fuel storage or high-temperature (>1500Â K) steam oxidation linked to reactor safety. This paper attempts to unify modelling for air oxidation of UO2 fuel over a wide range of temperature, and thus to assist future improvement of the ASTEC code, co-developed by IRSN and GRS. Phenomenological correlations for different temperature ranges distinguish between oxidation on the scale of individual grains to U3O7 and U3O8 below â¼700Â K and individual fragments to U3O8 via UO2+x and/or U4O9 above â¼1200Â K. Between about 700 and 1200Â K, empirical oxidation rates slowly decline as the U3O8 product becomes coarser-grained and more coherent, and fragment-scale processes become important. A more mechanistic approach to high-temperature oxidation addresses questions of oxygen supply, surface reaction kinetics, thermodynamic properties, and solid-state oxygen diffusion. Experimental data are scarce, however, especially at low oxygen partial pressures and high temperatures.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Peter Taylor,