► In this study we propose two alternatives for super critical water (cooled) nuclear power plants (SCWR NPPs) that will be able to produce a net mechanical power of 1200-MW. A first solution consists of a single unit while the second one requires two identical (600-MW) systems. ► Each plant uses thermodynamic cycles based on a conventional supercritical water power plant to be built in Russia. However, its application to a nuclear power station has required some modifications. ► Both, the actual plant design as well as the modified one are modeled and simulated. In general, the results are in good agreement with the existing data. The models are then used to perform an optimization process based on the use of genetic algorithms. ► The fronts of Pareto show that the results of the original plant design are quite close to those obtained from our optimization. Furthermore, the optimization procedure clearly indicates that it is still possible to increase both the net mechanical power and plant efficiency by only changing few decision variables. ► Two 600-MW SCWR NPPs will necessitate doubling mechanical and nuclear components that increases investment and operational cost. A single 1200-MW SCWR NPP requires higher mass flow rates, which involve dimensioning of major thermal components, i.e., turbines, heat exchangers, main circuit pumps, etc. These modifications affect the internal power requirement and have an effect on the overall plant performance. A trade-off between two NPP possibilities requires a multi-objective optimization that should include economic models. As member of the Generation IV International Forum (GIF), Canada has decided to orient its efforts towards the design of a CANDU-type SuperCritical Water-cooled nuclear Reactor (SCWR). Such a system must run at a coolant outlet temperature of about 625 °C and at a pressure of 25 MPa. Even though several steam-cycle arrangements used in existing thermal-power plants have been discussed by many authors, none of the proposed cycles have been optimized and adapted to the pressure-channel SCWR concept. The present work is intended to fulfil this gap by including at least two alternative solutions of SCWR power cycles that could reheat the supercritical water in the reactor core to achieve a net mechanical power of 1200-MW. Thus, thermodynamic models for preselected power cycles, their validation among existing data as well as their optimization using an “evolutionary optimization” technique based on genetic algorithms are presented and discussed.