[en] In order to evaluate the accuracies of the kinetics parameters predicted with the continuous-energy Monte Carlo calculation code, MVP3, core analysis was performed for light-water moderated UO₂ and mixed oxide (MOX) fuel cores for which the ratios of effective delayed-neutron fraction (β_eff) to prompt-neutron life time (ℓ) - represented hereafter by β_eff/ℓ - and β_eff values were measured. The results obtained with the JENDL-4.0-based neutron library showed that (the calculation values (C)/the measurement values (E)−1) ranged from -1.0% to 4.0% for the β_eff/ℓ values with an average of 1.0% and a standard deviation of 1.1% for the 17 cores (the UO₂, and UO₂-MOX mixed cores) tested in the Tank-Type Critical Assembly (TCA). With respect to the β_eff of one UO₂ core in TCA, C/E -1 was 1.2%. For the β_eff values of the UO₂ and MOX cores tested in the EOLE critical facility, C/E - 1 was -1.5% for the former and -4.6% for the latter. The calculated β_eff value of the MOX core using the JEFF-3.2-based neutron library was larger by 4% than that calculated using the JENDL-4.0-based neutron library and showed better agreement to the measurement. (author)