A theoretical analysis of UO2-PuO2 fueled, light water moderated lattice experiments has been performed to aid in establishing technical bases and design criteria for the utilization of plutonium-bearing fuel in thermal power reactors. Results for UO2 and Al-Pu lattices are included to understand the effects due to uranium and plutonium separately. The problems involved in calculating critical experiments are discussed. Estimates of the effects of various approximations inherent in the theoretical methods and/or analysis procedures are included along with the consequence on the results of the correlation. Uncertainties in the measurements and the neutron cross-section data are related to uncertainties in the calculated values of keff. Areas which should be investigated in future analyses are also identified.