Open AccessANL Pre Analysis of the SHEBA/CERES Experiment
Author(s) -
G. Palmiotti,
Michael S. Smith,
R. T. Klann,
E.K. Fujita,
G. Imel
Publication year - 1999
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/757501
Subject(s) - burnup , criticality , nuclear engineering , fission products , uranium , uranium oxide , natural uranium , fission , enriched uranium , mox fuel , environmental science , spent nuclear fuel , fission product yield , fuel element failure , thorium fuel cycle , neutron capture , nuclear fuel , nuclear physics , nuclear reactor , neutron , engineering , physics
The French and British nuclear programs have prepared a series of natural uranium oxide fuel samples spiked with small amounts of the individual fission products which makeup a large fraction of the total neutron absorption by fission products in spent nuclear fuel. Both programs have utilized these samples in experimental reactors and have inferred the worth of the individual fission products. These results have been used to validate the cross sections used in criticality safety calculations. These measurements constitute a major element in support of spent fuel burnup credit in these countries
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