The operation of boiling water reactors to date offers a wealth of operating data useful in evaluating the adequacy of existing operations analysis methods. Recent experience during the first fuel cycle of the KRB and Garigliano reactors has yielded considerable information on operating power distribution, fuel cycle lengths, and criticality predictions. The in-core neutron monitoring systems of the most recent BWR's allow experimental determination of operating power distributions in both the radial and axial dimensions. Recent methods developments in power distribution solutions and fuel cycle analysis have resulted in excellent predictive and postoperative analysis of core performance. Effects of control rod, steam void, and fuel exposure distributions on radial power distributions, and neutron multiplication factors are observed to be quite well represented with existing boiling water reactor digital computer simulators using three-dimensional fast-neutron flux solutions with thermal hydraulic feedback.