Migration of Metallic Fission Products in Reactor Oxide Fuels
- 1 August 1977
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 35 (1) , 80-86
- https://doi.org/10.13182/nt77-a31851
Abstract
The fission-product elements molybdenum and ruthenium were added to uranium and uranium-plutonium oxide by a co-precipitation technique. Heat treatment of these materials in a simulated reactor thermal gradient causes migration and coagulation of the metals to form inclusions up to a maximum size of 10 m. Inclusions of large diameters between 5 and 10 µm do not migrate noticeably by diffusion. Their migration rate is different from that of pores in a temperature gradient.Keywords
This publication has 11 references indexed in Scilit:
- Consideration of the simulation of in-pile radial temperature profiles in mixed-oxide fuel pinsJournal of Nuclear Materials, 1973
- In-pile migration of fission product inclusions in mixed-oxide fuelsJournal of Applied Physics, 1973
- Surface diffusion, surface free energy, and grain-boundary free energy of uranium dioxideJournal of Nuclear Materials, 1971
- Analysis of fission product ingots formed in uranium-plutonium oxide irradiated in EBR-IIJournal of Nuclear Materials, 1970
- Examination of neutron-irradiated UO2 using the scanning electron microscopeJournal of Materials Science, 1970
- Kinetics of diffusional motion of pores in solidsJournal of Nuclear Materials, 1969
- Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron fluxJournal of Nuclear Materials, 1969
- Metallic fission-product inclusions in irradiated oxide fuelsJournal of Nuclear Materials, 1968
- Microanalysis of inclusions in irradiated UO2Journal of Nuclear Materials, 1967
- Electron probe micro-analysis of irradiated UO2Journal of Nuclear Materials, 1965