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Enhancing Nuclear Safety


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Estimation of the Grain Boundary Gas Inventory in MIMAS/AUC MOX Fuel and Consistency with REP-Na Test Results


Journal title : Journal of Nuclear Science and Technology
Volume : 43
Issue : 9
Pagination : 1105-1113 
Publication date : 01/09/2006

Document type > *Article de revue

Keywords > CABRI (Test reactor for fuel safety), helium, high burn-up, MOX, RIA

Research Unit > IRSN/DPAM/SEMCA/LEC

Authors > LEMOINE Francette

Publication Date > 01/09/2006

Summary

In the frame of its research activities on fuel safety, the French 'Institut de Radioprotection et de sûrete Nucléaire' performed the REP-Na program in the CABRI reactor devoted to the study of Reactivity Initiated Accidents. Focused on high burn-up UO2 and MOX fuel behaviour, twelve tests (8 UO2 and 4 MOX) were realized from 1993 to 2000. In all these tests, the influence of grain boundary gas was evidenced and it appeared necessary to perform some estimation of its inventory in irradiated fuel. Such evaluations are presented for the MOX MIMAS/AUC fuel, based on two different approaches: 'experimental' and 'theoretical.' The fission gas amount located at the grain boundaries increases with burn-up in correlation with the production, but also with the initial Pu enrichment, as soon as the agglomerates have reached the full restructuring threshold for the High Burn-up Structure. The consistency with the REP-Na test results is checked, showing that a significant cladding deformation is needed, clearly higher than for UO2 fuel in order to release all the grain boundary gas in RIA. Furthermore, to the fission gas effect, adds the helium's occluded in the irradiated fuel whose amount increases with burn-up, Pu enrichment and 241Pu and 241Am initial content.
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