Analysis of the nearly homogeneous enriched uranium-graphite critical assemblies described in the preceding paper by Phelps and Weinstock are reported in this paper. These assemblies are characterized mainly by their high leakage rate, and two methods are used for estimating the leakage: 1) the conventional B1 approximation method and 2) the moments method using Monte Carlo calculations for the moments of the slowing down distribution. It is found that the B1 approximation describes the leakage effects quite accurately. Most of the cross sections used in the calculations are from the recent evaluated nuclear data file (ENDF/B). Results of calculations for keff, neutron lifetimes, and foil activation ratios are generally in excellent agreement with the measurements.