Monte Carlo Analysis of Thermal-Spectrum Averaged Measurements of <i>&eta;</i> of Uranium-233 and Uranium-235

M. Goldsmith and J. J. Ullo

doi:dx.doi.org/10.13182/NSE76-A26882

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Home / Publications / Journals / Nuclear Science and Engineering / Volume 60 / Number 3

Monte Carlo Analysis of Thermal-Spectrum Averaged Measurements of η of Uranium-233 and Uranium-235

M. Goldsmith and J. J. Ullo

Nuclear Science and Engineering / Volume 60 / Number 3 / July 1976 / Pages 251-261

Technical Paper / dx.doi.org/10.13182/NSE76-A26882

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Monte Carlo analysis of the Oak Ridge National Laboratory measurements of the fission neutron yield due to the absorption of a 2200 m/sec neutron in ²³³U and ²³⁵U, respectively, yields: = 2.3019 ± 0.0086 and = 2.0746 ± 0.0078. The analysis was confirmed by calculating measured quantities employed by the experimentalists in their determinations of η₂₂₀₀.