Abstract
A review is given on the chemical behaviour of the fission products in steady-state operated nuclear oxide fuels. The evaluation of irradiation experiments results in the description of the release, the transport properties and the alloying and reaction behaviour of the fission products in their different chemical states. Out-of-pile results are presented on the solubility of some fission product oxides in UO 2 and (U, Pu)O 2 and on the phase behaviour of selected multi-component fission product systems. The consequences for the melting point, the thermal conductivity and the shift of the O M -ratio of irradiated oxide fuels are outlined. The paper is complemented by a synopsis of the methods of the elemental analysis on irradiated materials in a micrometer scale.
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