journal article·2003-07

The EFTTRA-T3 irradiation experiment on inert matrix fuels

E.A.C Neeft, K Bakker, R.P.C Schram, R Conrad, R.J.M Konings

Journal of Nuclear Materials· Volume 320· Issue 1-2
Publisher page

Abstract

Abstract In the EFTTRA-T3 irradiation experiment eight uranium bearing inert matrix fuel capsules and eight capsules containing inert matrices have been irradiated. The irradiations were based on the matrices: MgO, MgAl 2 O 4 , Y 3 Al 5 O 12 , Y 2 O 3 and CeO 2 . The heterogeneously dispersed fuel contained fissile inclusions of UO 2 or (U,Y)O x . These capsules were irradiated for 198.87 days in the HFR Petten. The burn-up of the U-bearing capsules was 17–20% FIMA. The present paper describes all aspects of the EFTTRA-T3 irradiation; the fabrication and characterisation of the samples, irradiation and both destructive and non-destructive PIE.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear materials and radiation effects

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References (13)

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