The fabrication and irradiation of plutonium-containing inert matrix fuels for the ‘Once Though Then Out’ experiment
作者： F Ingold , R.P.C Schram , R.R van der Laan , F.C Klaassen , K Bakker
DOI: 10.1016/S0022-3115(03)00143-0
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摘要: Abstract Seven plutonium containing inert matrix fuel (IMF) capsules were prepared for an irradiation experiment in the high flux reactor. In experiment, named once-through-then-out, both spinel-based and zirconia-based targets are irradiated up to a burnup of about 200 GW d m−3, corresponding Pu depletion 50–60%. Both micro macrodispersed spinel tested, zirconia homogeneous type. this paper, fabrication routes IMF pellets described detail. The results dimensional measurements, density ceramographies X-ray images samples given. Some preliminary included.
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