[en] Full text: Out of a great many of new power technologies, fission nuclear power is the only realistic way to stop the growth in extraction and combustion of fossil fuel. However, this is something to be achieved only through the nuclear power to have by the mid-21st century the capacity an order of magnitude as high as the current level. Nuclear power of such a scale will necessitate a new nuclear technology which is required to provide: transition to power with unlimited fuel resources; economically competitive nuclear power through reducing the cost of building and operating NPPs of a high inherent safety level with highly efficient utilization of fuel and generated heat; elimination of severe accidents with radioactive release which require evacuation of population, to be achieved primarily through combining inherent safety, passive protection features and impossible loss of lead coolant; an environmentally safe closed fuel cycle with in-pile combustion of minor actinides and radiation-equivalent disposal of radioactive waste; creation of nuclear proliferation barriers by way of eliminating uranium enrichment and plutonium separation facilities. These problems are solved in the BREST lead-cooled fast reactor. The initial stage plan is to build an NPP with a demonstration reactor and an on-site fuel cycle to verify designs, try out processes involving lead using as the coolant and study the behavior of the reactor and its systems and components in different modes, including resistance to anticipated operational occurrences and accidents simulated on the reactor. This will be followed by a rapid transition to a fast lead-cooled power reactor of 1200 MW(e) featuring two- circuit heat removal from the core to the turbine with supercritical steam parameters. The state of the activities to develop the NPP with lead-cooled fast reactors and an on-site fuel cycle is presented. A core with a moderate power rating has been considered. This will have a uranium-plutonium mononitride fuel, a lead reflector, a widely spaced fuel lattice, levelled-off and stabilized lead and fuel cladding temperatures, a high breeding coefficient CBR ∼1, negative power and temperature reactivity coefficients and a negative void effect. Emergency processes have been analyzed and found not leading to prompt-neutron runaway of the reactor, loss of coolant, fires and explosions to involve fuel damage and catastrophic radioactive release even when the external barriers are broken and all active safety features fail. Perfect utilization of fuel and high efficiency, simplification of structures and elimination of complex engineered safety and accident localization systems are prerequisites for reactor economic competitiveness. Basic NPP, reactor, on-site fuel cycle and RW processing structures as well as the results of experimental studies to support the approaches taken are presented. (author)