Stoichiometric Effects on Performance of High-Temperature Gas-Cooled Reactor Fuels from the U-C-O System
- 1 September 1977
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 35 (2) , 428-441
- https://doi.org/10.13182/nt35-428
Abstract
Two fuel failure mechanisms were identified for coated particle fuels that are directly related to fuel kernel stoichiometry. These mechanisms are thermal migration of the kernel through the coating layers and chemical interaction between rare-earth fission products and the silicon carbide (SiC) layer (the primary barrier to diffusion of metal fission products out of the particle) leading to failure of the SiC layer. Thermal migration appears to be most severe for oxide fuels, while chemical interaction is most severe with carbide systems.Thermodynamic calculations indicated that oxide-carbide fuel kernels may permit a stoichiometry that reduces both problems to manageable levels for currently planned high-temperature gas-cooled reactors. Such stoichiometry adjustment is possible over the complete spectrum from UO2 to UO2 for the present recycle fuel, a weak acid resin (WAR)-derived fissile kernel. Thermodynamic calculations indicate that WAR kernels containing 85% UO2) will develop excessive C...Keywords
This publication has 10 references indexed in Scilit:
- Influence of Irradiation Temperature, Burnup, and Fuel Composition on Gas Pressure (Xe, Kr, CO, CO2) in Coated Particle FuelsJournal of the American Ceramic Society, 1976
- Estimation of Gibbs Free Energy FunctionsJournal of the American Ceramic Society, 1976
- Apparatus for measuring gases from irradiated fuel particlesJournal of Nuclear Materials, 1975
- Kernel Migration in Coated Carbide Fuel ParticlesNuclear Technology, 1975
- Applications of thermodynamics for predicting and understanding the performance of fast breeder reactor oxide fuelsJournal of Nuclear Materials, 1974
- Cesium molybdate, Cs2MoO4: Heat capacity and thermodynamic properties from 5 to 350 KThe Journal of Chemical Thermodynamics, 1974
- Thermodynamic data for U-Ce-oxidesJournal of Inorganic and Nuclear Chemistry, 1970
- Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron fluxJournal of Nuclear Materials, 1969
- Thermodynamic Properties of Uranium Carbides via the U-C-O System.Journal of Chemical & Engineering Data, 1966
- Phase Relations in the System Uranium—Carbon—OxygenJournal of the American Ceramic Society, 1964