Author/Authors :
J.P.A. Neeft، نويسنده , , E.A.C. and Bakker، نويسنده , , K. and Belvroy، نويسنده , , R.L. and Tams، نويسنده , , W.J. and Schram، نويسنده , , R.P.C. and Conrad، نويسنده , , R. and van Veen، نويسنده , , A.، نويسنده ,
Abstract :
Macro-dispersed inert matrix fuels were irradiated in the high flux reactor in Petten. These fuels consisted of UO2 inclusions embedded in the inert matrices MgO, MgAl2O4, Y3Al5O12, CeO2-x and Y2O3. The uranium burn-up reached 17.1–19.8% FIMA after an irradiation period of 198.9 days. The sample temperature was about 700–1000 K. Room temperature indentation measurements were performed in the inert matrices before and after irradiation to determine the Vickers hardness and the fracture toughness. The volume swelling of the UO2 inclusions has been determined. Pellets of UO2 inclusions embedded in MgO, MgAl2O4 and Y3Al5O12 show cracks in the matrix between these inclusions after neutron irradiation. A model is used to describe the fracture behaviour of these inert matrix fuels.
