Co-generation Nuclear Power Plant with Innovative Simplified Passive Boiling Water Reactor VK-300

摘要

In Russia, heat is produced predominantly at heat-and-power co-generation plants, which is the most efficient option. At present, work is under way to develop a dedicated reactor for nuclear co-generation plants. The reactor is expected to meet the following requirements specific for such plants: high reliability essential for uninterrupted heat supply, high safety, to allow building nuclear co-generation plants not far from cities, economic competitiveness despite small unit capacity typical for nuclear co-generation plants (200 to 250 MWe). The innovative reactor facility VK-300 has been designed on the basis of well-established nuclear technologies, proven major components, the operating experience of the prototype reactor VK-50 in RIAR, Dimitrovgrad, and the experience in designing such reactors as SBWR (GE) and SWR (Siemens). Thus, the reactor pressure vessel, fuel elements and moisture separators developed for WWER-1000 reactor facility were taken for VK-300.The description is focused on the most important design features of VK-300. More attention is given to the specific features of the reactor design related to original and efficient scheme of coolant circulation and separation top placement of control protective system (CPS) drive mechanisms unique system for reactor core emergency cooling. Reactor passive safety features is given a special emphasis. The original lay-out of the plant is described. In accordance with increased safety requirements for co-generation plants the reactor and turbine facilities are placed inside a common containment. The prospects for developing in Russia the nuclear power units with VK-300 reactor facility are analyzed.