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Title Проект реактора БН-900: выпускная квалификационная работа специалиста: 14.05.01 - Ядерные реакторы и материалы ; 14.05.01_01 - Ядерные реакторы
Creators Макаров Андрей Юрьевич
Scientific adviser Рассказов Виктор Васильевич
Other creators Свецинская Татьяна Григорьевна
Organization Санкт-Петербургский политехнический университет Петра Великого. Институт ядерной энергетики
Imprint Сосновый Бор, 2019
Collection Выпускные квалификационные работы; Общая коллекция
Subjects проект БН-900; быстрый реактор; геометрический расчет реактора; теплогидравлический расчет реактора; нейтронно-физический расчет реактора; система контроля целостности технологических каналов; технико-экономические показатели; охрана труда; BN-900 project; fast reactor; geometric calculation of the reactor; thermo-hydraulic calculation of the reactor; neutron-physical calculation of the reactor; techological chanels integryrty system; technical and economical data; protection of labour
Document type Specialist graduation qualification work
File type PDF
Language Russian
Level of education Specialist
Speciality code (FGOS) 14.05.01
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/vr19-41
Rights Доступ по паролю из сети Интернет (чтение, печать, копирование)
Record key ru\spstu\vkr\591
Record create date 4/19/2019

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В ходе выполнения работы произведен выбор основного и вспомогательного оборудования энергоблока. Проведены нейтронно-физический, тепло-гидравлический расчёты активной зоны реактора БН-900. Осуществлено определение технико-экономических показателей проектируемой атомной электростанции с расчетом показателей экономической эффективности проекта. Выполнено планирование действий по защите персонала и населения в случае возникновения аварий на АЭС. Выполнена графическая часть дипломного проекта.

Рurpose Subject of diploma project is a design of NPP with a capacity of 1,800 MW and with two BN-900 reactors . It’s main purpose is the production of electricity in the Trans-Baikal Territory. Its operation will enhance opportunities for development of the region due to the increase in electricity generation and replacement of decommissioned (state district power stations)GRES. So it is necessary to choose main equipment and make neutron-physical, thermal-hydraulic and economic calculations. Design / Methodology / Approach Neutron-physical parameters were calculated by four-group approximation method using four zones reactor model with end and side reflectors. Сhanges of the temperature of coolant, fuel cladding and in the center of the fuel pellet were determined by thermal hydraulic calculation . The calculation of technical and economic indicators allowed us to estimate the cost of construction of NPP and other economic indicators. Special Task Subject of special task is technological channels integrity system «TCIS». TCIS is an integral part of the gas circuit system of the reactor. TCIS system is an integral part of the gas circuit system of the reactor . It is designed to identify leaky channels when the reactor is operating in the energy mode. The modernization directed at reducing the number of technological channels belonging to one group is considered. Findings. Designed BN -900 reactor is safe from the point of view of neutron-physical and thermo-hydraulic calculation results. The main equipment of the plant was chosen. 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 BN is advisable.

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