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Migration of Metallic Fission Products in Reactor Oxide Fuels

F. D’Annucci, C. Sari, G. Schumacher

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 80-86

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31851

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.