Abstract
In this work the Water-Reflected 91-Liter Sphere of Enriched Uranium Oxyfluoride Solution experiment from the International Handbook of Evaluated Criticality Safety Benchmark Experiments is simulated with a neutron transport Monte Carlo simulator. The simulator works with continuous variables of the phase space relevant in transport theory, which allows to extract the simulated spectral neutron flux and render it in parameterized representation. The neutron effective multiplication factor is calculated and compared to the experimental findings, as well as to results from other simulation codes. Agreement between experiment and the present simulation was found to be within one standard deviation.
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