Выполнено проектирование атомной электростанции мощностью 3000 МВт с реакторами типа BWR-1000. Произведен выбор основного и вспомогательного оборудования энергоблока. Осуществлен расчет тепловой схемы энергоблока АЭС на номинальном режиме работы и при работе на 75% от номинальной мощности. Проведены геометрический, нейтронно-физический и теплогидравлический расчеты реактора. Исследован газовый контур реактора РБМК-1000. Осуществлено определение технико-экономических показателей проектируемой атомной электростанции. Осуществлена компоновка и выбор электрооборудования АЭС. Рассмотрены вопросы охраны труда. Выполнена графическая часть дипломного проекта.

Subject: “Nuclear Power Plant with BWR-1000” Purpose Subject of this diploma project is a design of NPP with a capacity of 3000 MW and with nuclear reactors BWR-1000 which general purpose is electricity production in the Tomsk region as electricity generated there is not enough for internal consumption in the region. It is necessary to choose main and auxiliary equipment, to make geometrical, neutron-physical, thermal-hydraulic and economical calculations. Design / Methodology / Approach Neutron-physical parameters of fuel cell were calculated by multigroup approximation method when for reactor ones two-group approximation method took place. Calculations were made in the «Sapfir-95» program. Special Task Subject of special task is «The study of the chemical regime of the gas circuit of the RBMK-1000 Leningrad NPP». The gas circuit of the reactor is a system of normal operation, important for safety, so the analysis of components is an integral process that is carried out promptly. The analysis of gas media and the analysis of the causes of the increased concentrations of the components of the gas mixture are made. Findings Designed BWR-1000 reactor is safe from the point of view of neutron-physical and thermo-hydraulic calculation results. On the basis of technical and economical results it can be approved that the cost of electricity is quite low, the projected NPP has reasonable pay-back period. It can be expected that the creation of the reactor facility based on BWR is advisable.