The fundamental design of BREST-OD-300 and BREST-1200 reactors is presented. It is shown that it is necessary to develop nuclear energy complexes based on the BREST nuclear system. The stages, the status of scientific research and development work over the entire nuclear power complex, and the results of an expert analysis of the BREST-OD-300 design are presented. Nuclear Power Complex.To meet the requirements imposed on large-scale nuclear power, the questions of a closed nuclear fuel cycle and fuel regeneration become fundamental, since the duration of the extra-reactor part of the cycle must be as short as possible.The residence time of fuel in the BN-800 fast sodium reactor is 1.4 years. In water-chemical fuel recovery at a centralized plant, the duration of the part of the fuel cycle outside the reactor is ~7 yr, i.e., there will be five times more fuel outside than inside the reactor. In addition, it will be possible to put six times fewer fast reactors into operation using the plutonium from the irradiated fuel of thermal reactors. The number of fast reactors operating on excess plutonium from fast reactors will also decrease by a factor determined by the ratio T in /(T in + T out ), where T in is the fuel run in the reactor and T out is the duration of the extra-reactor part of the fuel cycle, as if the excess breeding (BR − 1) was less by the same factor. Then, plutonium breeding in fast reactors becomes pointless.It follows that a closed nuclear fuel cycle for fast reactors must be on-site and fuel recovery must permit working with high-level fuel. This is also supported by the shipment of fresh and irradiated uranium-plutonium fuel to a centralized plant. Shipping fuel from one BREST-1200 reactor to a single plant (based on experience VVÉR-440) will require 10 railroad cars per year, and correspondingly 100 reactors will require 1000 cars (approximately 6 cars per day: three in and three out). In so doing, 8000 containers with high-level nuclear fuel (50-100 kg plutonium per container) will be used, which will require accident measures, radiation safety measures, and adherence to a nonproliferation regime, all of which are difficult to ensure at the present time.When long-lived actinides are burned in a reactor, only fission products will be present in the repository for radioactive wastes. After a holding time of 150-200, years the fission products can be buried at the uranium mining site without destroying the natural level of radioactivity and without long-distance shipments of high-level materials.Thus, a nuclear power complex must consist of a nuclear power plant, a nuclear fuel cycle on the plant site, and a waste repository on the plant site.Design of the BREST-1200 Reactor System. The BREST-1200 reactor system is a two-loop steam-generating power-generating unit, which contains a reactor with steam generators, pumps, equipment for reloading fuel assemblies, a safety and control rod system, a concrete shaft with a heat shield, a steam-turbine unit, systems for removing heat during
Dynamic developing of modern nuclear industry demands meeting the following requirements: improved safety, reduced capital costs, radioactive waste (RW) management issues, independence of limited resources. Efficiency of uranium resources used in "BREST" reactors based on a closed fuel cycle is about 160 times higher than for VVER, RBMK reactors [1], which makes it possible to stop searching for new deposits and uranium mining. The need for periodical fuel regeneration and fabrication in a closed cycle includes reproduction of plutonium in the core without the uranium containing screens (breeding ratio is approximately 1,05, ensuring a high level of safety and support of the non-proliferation regime) and transmutation of the most dangerous long-lived actinides and high refining of RW, achieving the radiation balance of buried RW and extracted uranium ore. The manufacturing is located directly at the NPP to avoid transportation of fissile materials. This approach provides economic efficiency of the entire complex.
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