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In the Superfact experiment four oxide targets containing high and low concentrations of 237Np and 241Am, representing the homogeneous and heterogeneous in-pile recycling concepts, were irradiated in the PHENIX reactor. The burnup reached 6.4 % FIMA in the targets with low concentrations of Np and Am and 4.5 % FIMA in the targets with high concentrations of Np and Am. About 25 % of initial concentrations of 237Np and 241Am was transmuted. Generally, the radial distribution of Np and Am was quite flat indicating an even rate of transmutation over the pellet cross-section. In the targets with 45 % and 20 % Np, 10 and 12 wt % Pu was created; most of this was 238Pu with a half-life of 88 y. All the targets exhibited high fission gas release of 67 to 77 %. As with standard LMFBR oxide fuel, Cr(2)O(3) was the main product of fuel-cladding chemical interaction. In the target containing 20 % Am, an Fe-Pd alloy was present in all the major radial cracks.

Additional information

Authors: WALKER C T, JRC Karlsruhe (DE);NICOLAOU G, JRC Karlsruhe (DE)
Bibliographic Reference: Article: Journal of Nuclear Materials, Vol. 218 (1995) pp. 129-138
Record Number: 199510555 / Last updated on: 1995-04-21
Original language: en
Available languages: en