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This paper reviews the contributions that on-going or completed research programmes at the European Institute for Transuranium Elements have made to the existing knowledge of the behaviour of UO(2) and MOX fuels. In these programmes the influence of burn-up on fuel restructuring and fission gas release, under both steady-state and transient irradiation conditions, have been or are being investigated, using fuels from power and test reactors. In the particular case of MOX fuel, the morphology of the Pu-rich particles, fission product behaviour and U/Pu interdiffusion have been studied in detail. The principal aim of the paper is to highlight the microstructural changes which occur as a consequence of an increase in burn-up. The data reported were obtained using a wide range of experimental techniques, including scanning electron microscopy, electron probe microanalysis and quantitative optical microscopy.

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Authors: WALKER C T, JRC Karlsruhe (DE);COQUERELLE M, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: International Topical Meeting on LWR Fuel Performance, Avignon (FR), April 21-24, 1991
Availability: Available from (1) as Paper EN 35900 ORA
Record Number: 199110234 / Last updated on: 1994-12-02
Original language: en
Available languages: en