title: ÐÑÐ¾ÐµÐºÑ ÐÐ­Ð¡ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑÑ 3200 ÐÐÑ Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°Ð¼Ð¸ BWR-800
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° ÑÐ¿ÐµÑÐ¸Ð°Ð»Ð¸ÑÑÐ°
titleType: Subtitle
title: 3200 MW capacity NPP project with BWR-800 reactors
Creators: name: Ð¢ÐµÑÐµÑÐµÐ½ÐºÐ¾, ÐÐ¼Ð¸ÑÑÐ¸Ð¹
Publisher: name: Ð¡Ð°Ð½ÐºÑ-ÐÐµÑÐµÑÐ±ÑÑÐ³ÑÐºÐ¸Ð¹ Ð¿Ð¾Ð»Ð¸ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ½Ð¸Ð²ÐµÑÑÐ¸ÑÐµÑ ÐÐµÑÑÐ° ÐÐµÐ»Ð¸ÐºÐ¾Ð³Ð¾
Year: 2019
Subjects: Ð ÐµÐ°ÐºÑÐ¾Ñ BWR-800
ABWR
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BWR-800
advanced boiling water reactor
NPP thermal scheme
four-group approximation method
sealed storage of spent fuel assenbly in the cooling pool of Leningrad NPP

description: ÐÑÐ¿Ð¾Ð»Ð½ÐµÐ½Ð¾ Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð°ÑÐ¾Ð¼Ð½Ð¾Ð¹ ÑÐ»ÐµÐºÑÑÐ¾ÑÑÐ°Ð½ÑÐ¸Ð¸ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑÑ 3200 ÐÐÑ Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°Ð¼Ð¸ ÑÐ¸Ð¿Ð° BWR-800. ÐÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÐµÐ½ Ð²ÑÐ±Ð¾Ñ Ð¾ÑÐ½Ð¾Ð²Ð½Ð¾Ð³Ð¾ Ð¸ Ð²ÑÐ¿Ð¾Ð¼Ð¾Ð³Ð°ÑÐµÐ»ÑÐ½Ð¾Ð³Ð¾ Ð¾Ð±Ð¾ÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ°. ÐÑÑÑÐµÑÑÐ²Ð»ÐµÐ½ ÑÐ°ÑÑÐµÑ ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÑÐµÐ¼Ñ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° ÐÐ­Ð¡ Ð½Ð° Ð½Ð¾Ð¼Ð¸Ð½Ð°Ð»ÑÐ½Ð¾Ð¼ ÑÐµÐ¶Ð¸Ð¼Ðµ ÑÐ°Ð±Ð¾ÑÑ Ð¸ Ð¿ÑÐ¸ ÑÐ°Ð±Ð¾ÑÐµ Ð½Ð° 50% Ð¾Ñ Ð½Ð¾Ð¼Ð¸Ð½Ð°Ð»ÑÐ½Ð¾Ð¹ Ð¼Ð¾ÑÐ½Ð¾ÑÑÐ¸. ÐÑÐ¾Ð²ÐµÐ´ÐµÐ½Ñ Ð³ÐµÐ¾Ð¼ÐµÑÑÐ¸ÑÐµÑÐºÐ¸Ð¹, Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ð¹ Ð¸ ÑÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑÑ ÑÐµÐ°ÐºÑÐ¾ÑÐ°. ÐÑÑÑÐµÑÑÐ²Ð»ÐµÐ½Ð¾ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ ÑÐµÑÐ½Ð¸ÐºÐ¾-ÑÐºÐ¾Ð½Ð¾Ð¼Ð¸ÑÐµÑÐºÐ¸Ñ Ð¿Ð¾ÐºÐ°Ð·Ð°ÑÐµÐ»ÐµÐ¹ Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÑÐµÐ¼Ð¾Ð¹ Ð°ÑÐ¾Ð¼Ð½Ð¾Ð¹ ÑÐ»ÐµÐºÑÑÐ¾ÑÑÐ°Ð½ÑÐ¸Ð¸. ÐÑÑÑÐµÑÑÐ²Ð»ÐµÐ½Ð° ÐºÐ¾Ð¼Ð¿Ð¾Ð½Ð¾Ð²ÐºÐ° Ð¸ Ð²ÑÐ±Ð¾Ñ ÑÐ»ÐµÐºÑÑÐ¾Ð¾Ð±Ð¾ÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÐÐ­Ð¡. Ð Ð°ÑÑÐ¼Ð¾ÑÑÐµÐ½Ñ Ð²Ð¾Ð¿ÑÐ¾ÑÑ Ð¾ÑÑÐ°Ð½Ñ ÑÑÑÐ´Ð°. ÐÑÐ¿Ð¾Ð»Ð½ÐµÐ½Ð° Ð³ÑÐ°ÑÐ¸ÑÐµÑÐºÐ°Ñ ÑÐ°ÑÑÑ Ð´Ð¸Ð¿Ð»Ð¾Ð¼Ð½Ð¾Ð³Ð¾ Ð¿ÑÐ¾ÐµÐºÑÐ°.
description: Subject of diploma project is a design of NPP with a capacity of 3200 MW and with nuclear reactors BWR-800. It is necessary to choose main and auxiliary equipment and make geometrical, neutron-physical, thermal-hydraulic and economic calculations. The ABWR was chosen as a prototype. Neutron-physical parameters were calculated by four-group approximation method, cell calculation and homogenization technique, Â«first collisionÂ» method, Amuayal-Benua-Gorovets technique, Honeck technique. As a comparison of the results, also the calculations were made in the programming package âSAPPHIREâ.The distribution of the energy release, the temperature changes of the coolant, fuel element cladding, in the center of fuel pellet were determined by the thermal-hydraulic calculation. Technical and economic parameters calculation allowed to estimate the cost of the NPP construction and other economic figures. Subject of special task is sealed storage of spent fuel assembly in the cooling pool of Leningrad NPP. The storage scheme for spent fuel assemblies in the cooling pools of the Leningrad plant is studied in detail. The calculations resultsof the infinite multiplication factoron the burnup of fuel for cooling pools with sealed storage of SFA. Designed BWR-800 reactor is safe from the point of view of neutron-physical and thermo-hydraulic calculation results. On the basis of technical and economical resultsit 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 ABWR is advisable.