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[en] In connection with the normal refuelling of French Pressurized Water Reactors with mixed oxide (MOX) fuel assemblies, a comprehensive experimental data yielded by this programme is the validation of general design of MOX rod, leading to improve its performance. An important point of this study is the behaviour of a defective MOX rod under irradiation, and especially the release rate of fission products. An experimental defective MOX fuel rod, named EDITHMOX 01, has been recently irradiated in the JET POMPE irradiation loop in the SILOE research reactor at the CEA's Nuclear Research Center in Grenoble. The results of the experiment show a release rate of fission products comparable to those obtained with uranium oxide. Metallographic analyses show an appreciable evolution of microstructure, with fission gas precipitation bubbles, due to fuel oxidation under water vapor conditions. 3 refs, 8 figs
Source
International Atomic Energy Agency, Vienna (Austria); 288 p; ISSN 1011-4289; 
; Jun 1993; p. 179-184; Technical committeee meeting on fuel failure in normal operation of water reactors: Experience, mechanisms and management; Dimitrovgrad (Russian Federation); 26-29 May 1992
; Jun 1993; p. 179-184; Technical committeee meeting on fuel failure in normal operation of water reactors: Experience, mechanisms and management; Dimitrovgrad (Russian Federation); 26-29 May 1992