EVALUATION OF MASS SPECTROMETRIC AND RADIOCHEMICAL ANALYSES OF YANKEE CORE I SPENT FUEL Page: 4 of 162
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This report presents the results of mass spectrometric, X-ray
spectrographic, and radiochemical analyses of spent fuel samples from
219 locations in the Yankee core. These sample locations were pre-
selected to provide: 1) the U and Pu isotopic composition of the fuel
as a function of burnup in the asymptotic and perturbed reactor neutron
spectra; 2) the spatial distribution of burnup and fuel isotopes in the
rods, in the assemblies, and in the core; 3) the total isotopic inventory
of the core; and 4) fuel characteristics, including the specific Pu pro-
duction, the effective capture-to-fission ratio in U-235, and the net mass
of fissile materials destroyed per unit of energy release in the fuel.
Values of burnup are inferred over a broad range (1,200 to 31,000
MWD/MTU) from relationships between U and Pu concentrations measured be-
fore and after irradiation, and from the activities of the Cs-137 and
Sr-90 fission products. The calculations used to infer burnup and the
various fuel characteristics from the spent fuel data are described in
The consistency and reliability of the data are established through
the evaluation of the experimental results obtained from a number of inter-
Zaboratroy cross-check and monitor sample solutions.
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Nodvik, R.J. EVALUATION OF MASS SPECTROMETRIC AND RADIOCHEMICAL ANALYSES OF YANKEE CORE I SPENT FUEL, report, March 1, 1966; Pittsburgh, Pennsylvania. (https://digital.library.unt.edu/ark:/67531/metadc1030968/m1/4/: accessed April 23, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.