Title: Проект АЭС мощностью 3000 Мвт с реакторами ВК-1000: выпускная квалификационная работа специалиста: 14.05.02 - Атомные станции: проектирование, эксплуатация и инжиниринг ; 14.05.02_01 - Проектирование и эксплуатация атомных станций
Creators: Давыденко Диана Юрьевна
Scientific adviser: Абдуллаев Али Мамедкерим оглы
Other creators: Свецинская Татьяна Григорьевна
Organization: Санкт-Петербургский политехнический университет Петра Великого. Институт ядерной энергетики (филиал) ФГАОУ ВО "СПбПУ" г. Сосновый Бор
Imprint: Сосновый Бор, 2019
Collection: Выпускные квалификационные работы; Общая коллекция
Subjects: BK-1000; кипящий водо-водяной реактор; метод четырех-группового приближения; восстановление ресурсных характеристик графитовой кладки; дополнительный поглотитель; паровой коэффициент реактивности; VK-1000; boiling water reactor; four-group approximation method; restoration of resource characteristics (rrc); additional absorber; steam coefficient of reactivity
Document type: Specialist graduation qualification work
File type: PDF
Language: Russian
Speciality code (FGOS): 14.05.02
Speciality group (FGOS): 140000 - Ядерная энергетика и технологии
Links: Приложение; Отзыв руководителя; Рецензия; Отчет о проверке на объем и корректность внешних заимствований
DOI: 10.18720/SPBPU/3/2019/vr/vr19-53
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В ходе выполнения дипломного проекта спроектирована атомная электростанция мощностью 3000 МВт с тремя реакторными установками типа VK-1000. Произведен выбор основного и вспомогательного оборудования энергоблока. Составлена тепловая схема, произведен ее расчет на номинальном режиме работы и при работе на 50% от номинальной мощности. Проведены геометрический, теплогидравлический и нейтронно- физический расчеты активной зоны реакторной установки. Произведен выбор электрооборудования АЭС. Выполнена экономическая оценка стоимости проекта и рассчитаны технико-экономические показатели. Рассмотрены вопросы охраны труда и обеспечения безопасной эксплуатации оборудования АЭС. При работе над спецзаданием был рассмотрен вопрос восстановления ресурсных характеристик графитовой кладки и влияния ее на паровой коэффициент реактивности.

Subject: “Nuclear Power Plant with VK-1000” Subject of my diploma project is a design of NPP with a capacity of 3000 MW with nuclear reactors VK-1000. The selected construction site is the city Chistye Bory, Kostroma region. The construction of such NPP in the selected region will serve as a good impetus for it`s development, infrastructure and economy. During the work on this project it is necessary to choose main and auxiliary equipment, make neutron-physical, thermal-hydraulic, technical and economical calculations, justify the choice of electrical equipment and develop graphic materials. Calculated parameters for electrical equipment correspond to the power supply system of this region. The calculation of the thermal scheme allowed to estimate the efficiency of NPP and select the necessary equipment. Neutron-physical parameters were calculated by four-group approximation method, cell calculation and homogenization technique, «first collision» method, Amuayal-Benua-Gorovets technique. In calculation we analyzed the distribution of the energy release, temperature change of FE cladding, the fuel kernel and the coolant, we determined the margin to critical heat flux, which is 2,2. It satisfies the necessary conditions. Technical and economical indicators allowed us to determine the cost of construction of nuclear power plant. It will be equal to 515361 million rubles. Special question is studying the restoration of resource characteristics (RRC) of a graphite laying and its influence on steam coefficient of reactivity. An object of a research is the Leningrad NPP, a large amount of graphite is removed from the core of the reactor during the work on RRC. With reduction of graphite amount in a zone the moderating share in water increases. The value of steam coefficient of reactivity decreases in number. As it significantly depends on loading of the core of the reactor, maintenance of value of steam reactivity coefficient is provided with loading (unloading) of additional absorber By means of the «SADCO» code calculations are made and the analysis of value change of steam coefficient of reactivity before the work on RRC is carried out. Calculation results showed that works on RRC influence the value of steam coefficient of reactivity. Designed VK-1000 reactor is effective from the point of view of neutron-physical and thermal-hydraulic calculation results. Reactor based on the VK in Russia will be a new stage in nuclear industry development. Technical and economical calculations have shown us that the cost of electricity is quite low. Also, there was defined a good parameter of payback period of the projected NPP. It can be concluded that the creation of the reactor facility is advisable, taking into account the principles and approaches contained in the requirements of the world`s users of nuclear energy and the IAEA recommendations.

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