[en] Following the release of ENDF/B-VII.0, an assessment of the impact of the new evaluated data on CANDU^R-type reactor calculations has been carried out at AECL. A series of full-core MCNP simulations of ZED-2 reactor experiments was performed in order to assess the ability of the new nuclear data in the modeling of the real physical processes. Another series of calculations was carried out using an incremental replacement of ENDF/B-VI.8 data with the corresponding ENDF/B-VII.0 in order to identify the major contributors to the changes in the simulation results. The calculations were carried out with two continuous-energy multi-temperature libraries created at AECL, one based on ENDF/B-VI.8 and the other on ENDF/B-VII.0 data. This paper shows that the neutron multiplication factor values of the ZED-2 experiments calculated with the new data are well clustered around unity, while an under-prediction of about 0.4 - 0.6% is present in the results obtained with ENDF/B-VI.8 data. This finding is in good agreement with the conclusion of the ENDF/B-VII.0 benchmarking that accompanied the official release of the new data, which states that, for the category of thermal spectrum low-enriched compound-fuel reactors, to which the Candu-type reactors belong, the new data improves the prediction of the neutron multiplication factor by about 0.5%. The same approach of incremental replacement of ENDF/B-VI.8 with ENDF/B-VII.0 data was applied to infinite Candu lattice calculations at several burnup stages. The results show that the changes in the simulation results are mainly due to new data for ²³⁸U, ⁹⁰Zr, ⁹¹Zr and ¹⁶O. (authors)