Mechanical behaviour of macro-dispersed inert matrix fuels

Macro-dispersed inert matrix fuels were irradiated in the high flux reactor in Petten. These fuels consisted of UO 2 inclusions embedded in the inert matrices MgO, MgAl 2O 4, Y 3Al 5O 12, CeO 2- x and Y 2O 3. The uranium burn-up reached 17.1–19.8% FIMA after an irradiation period of 198.9 days. The...

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Veröffentlicht in:	Journal of nuclear materials 2003-05, Vol.317 (2), p.217-225
Hauptverfasser:	Neeft, E.A.C., Bakker, K., Belvroy, R.L., Tams, W.J., Schram, R.P.C., Conrad, R., van Veen, A.
Format:	Artikel
Sprache:	eng
Schlagworte:	Applied sciences Energy Exact sciences and technology Fuels Nuclear fuels Preparation and processing of nuclear fuels
Online-Zugang:	Volltext
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