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Argonne National Laboratory Reports

By F. C. Franklin, E. R. Ebersole and R. R. Heinrich

Abstract

This report compares calculated reaction rates based on neutron-transport calculations in RZ and XY geometries with measured values from a low-power dosimetry test in EBR-II. Axial distributions of Uranium-235 and uranium-238 fission rates and uranium-238 capture rate are given for various radial locations along the length of the core and the axial reflectors, and along the length of the radial steel reflectors. Reaction rates, primarily at the reactor midplane, are given for a number of fission and capture reactions. The analytical RZ- and XY-geometry models used for the neutronics calculations are described

Topics: Breeder reactors., Neutrons., Dosimetry., Neutron transport theory -- Mathematics., Neutrons -- Capture., Nuclear fission.
Publisher: Argonne National Laboratory
Year: 1977
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Provided by: UNT Digital Library
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