A recent neutron wave experiment in a thermal-neutron multiplying assembly with and without control rods has been analyzed numerically in terms of transport theory. The code TASK was used for this purpose. The present study dealing with a highly 235U-enriched, compact, neutron-multiplicative uranium system indicates that the dispersion law of the assembly is very sensitive to transport effects and to the estimation of the leakage of the fast neutron population. The present calculations of neutron wave propagation in multiplicative systems show that this technique can be used as a highly sophisticated experiment for integral checks of neutron cross-section sets.