Transmutation of neptunium and americium in a fast neutron flux : EPMA results and KORIGEN predictions for the superfact fuels
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.
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