title: ÐÑÐ¾ÐµÐºÑ ÐÐ­Ð¡ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑÑ 600 ÐÐÑ Ñ ÑÐ´ÐµÑÐ½ÑÐ¼ ÑÐµÐ°ÐºÑÐ¾ÑÐ¾Ð¼ ÐÐÐ­Ð
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¼Ð°Ð³Ð¸ÑÑÑÐ°
titleType: Subtitle
title: Project of a 600 MW nuclear power plant in the province of Sakarya, Turkey
Creators: name: ÐÐ½ÐµÑ, ÐÑÐ¼Ð°Ð¸Ð»
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: 2024
Subjects: ÑÐµÐ°ÐºÑÐ¾Ñ ÐÐÐ­Ð -600
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ÑÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ
ÑÐµÐ¿Ð»Ð¾Ð²Ð°Ñ ÑÑ ÐµÐ¼Ð°
ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÐºÐ° Ð¢ÑÑÑÐ¸Ð¸
VVER-600 reactor
neutron-physical calculation
thermal-hydraulic calculation
thermal scheme
Turkey electricity

description: Ð Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ Ð²Ñ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 600 ÐÐÑ Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°Ð¼Ð¸ ÑÐ¸Ð¿Ð° ÐÐÐ­Ð -600. ÐÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÐµÐ½ Ð¸ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½ Ð²ÑÐ±Ð¾Ñ Ð¿Ð»Ð¾ÑÐ°Ð´ÐºÐ¸ ÑÐ°Ð·Ð¼ÐµÑÐµÐ½Ð¸Ñ ÐÐ­Ð¡, Ð²ÑÐ¿Ð¾Ð»Ð½ÐµÐ½ ÑÐ°ÑÑÐµÑ ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÑÐµÐ¼Ñ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° ÐÐ­Ð¡, ÑÐµÐ»ÑÑ ÐºÐ¾ÑÐ¾ÑÐ¾Ð³Ð¾ Ð±ÑÐ»Ð¸ Ð¾ÑÐ½Ð¾Ð²Ð½ÑÐµ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÑ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° ÐÐ­Ð¡ Ñ ÐÐÐ­Ð , Ð²ÐºÐ»ÑÑÐ°Ñ Ð´Ð°Ð²Ð»ÐµÐ½Ð¸Ñ Ð¸ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÑ Ð³ÐµÐ½ÐµÑÐ¸ÑÑÐµÐ¼Ð¾Ð³Ð¾ Ð¿Ð°ÑÐ°, Ð´Ð°Ð²Ð»ÐµÐ½Ð¸Ñ ÐºÐ¾Ð½Ð´ÐµÐ½ÑÐ°ÑÐ¸Ð¸, Ð¾Ð¿ÑÐ¸Ð¼Ð°Ð»ÑÐ½Ð¾Ð¹ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÑ Ð¿Ð¸ÑÐ°ÑÐµÐ»ÑÐ½Ð¾Ð¹ Ð²Ð¾Ð´Ñ, Ð° ÑÐ°ÐºÐ¶Ðµ ÑÐ¸ÑÐ»Ð¾ Ð¿Ð¾Ð´Ð¾Ð³ÑÐµÐ²Ð°ÑÐµÐ»ÐµÐ¹. Ð ÑÐ¾Ð´Ðµ ÑÐ°ÑÑÐµÑÐ° ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÑÐµÐ¼Ñ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° ÐÐ­Ð¡ Ð±ÑÐ»Ð¸ Ð²ÑÑÐ¸ÑÐ»ÐµÐ½Ñ ÑÐ°ÑÑÐ¾Ð´Ñ Ð¸ Ð¿Ð¾ÐºÐ°Ð·Ð°Ð½Ñ Ð² Ð¾ÑÐ½Ð¾Ð²Ð½ÑÑ ÑÑÐµÐ¼Ð°Ñ, ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ°Ñ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑ Ð¸ ÐÐÐ Ð±ÑÑÑÑÐ¾ Ð¸ Ð½ÐµÑÑÐ¾ ÐÐ­Ð¡. ÐÑÑÑÐµÑÑÐ²Ð»ÐµÐ½ ÑÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ ÑÐµÐ°ÐºÑÐ¾ÑÐ°, ÑÐµÐ»ÑÑ ÐºÐ¾ÑÐ¾ÑÐ¾Ð³Ð¾ Ð±ÑÐ» Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸Ðº, Ð½ÐµÐ¾Ð±ÑÐ¾Ð´Ð¸Ð¼ÑÑ Ð´Ð»Ñ Ð¾ÑÐµÐ½ÐºÐ¸ ÑÐµÐ¿Ð»Ð¾ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¾Ð¹ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ, Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð¸Ðµ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¾Ð³Ð¾ Ð¸ Ð¿ÑÐ¾ÑÐ½Ð¾ÑÑÐ½ÑÑ ÑÐ°ÑÑÐµÑÐ¾Ð² ÑÐµÐ°ÐºÑÐ¾ÑÐ°, Ð²ÑÐ±Ð¾Ñ Ð¾Ð±Ð¾ÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ Ð¿ÐµÑÐ²Ð¾Ð³Ð¾ ÐºÐ¾Ð½ÑÑÑÐ° ÑÑÑÐ°Ð½Ð¾Ð²ÐºÐ¸. ÐÐ»Ð°Ð³Ð¾Ð´Ð°ÑÑ ÐµÐ¼Ñ Ð²Ð¾Ð·Ð¼Ð¾Ð¶Ð½Ð¾ Ð¾Ð¿ÑÐµÐ´ÐµÐ»Ð¸ÑÑ ÑÐ»ÐµÐ´ÑÑÑÐ¸Ðµ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸ÐºÐ¸: ÑÐ°ÑÑÐ¾Ð´ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ ÑÐµÑÐµÐ· ÑÐµÐ°ÐºÑÐ¾Ñ; ÑÐ°ÑÐ¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ ÑÐ°ÑÑÐ¾Ð´Ð¾Ð² Ð¿Ð¾ ÐºÐ°Ð½Ð°Ð»Ð°Ð¼ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ; Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ðµ ÑÐ¾Ð¿ÑÐ¾ÑÐ¸Ð²Ð»ÐµÐ½Ð¸Ñ ÑÐ°Ð·Ð»Ð¸ÑÐ½ÑÑ ÑÑÐ°ÑÑÐºÐ¾Ð² ÐºÐ¾Ð½ÑÑÑÐ° ÑÐ¸ÑÐºÑÐ»ÑÑÐ¸Ð¸ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ, ÑÑÐµÐ¿ÐµÐ½Ñ Ð´ÑÐ¾ÑÑÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð¿Ð¾ÑÐ¾ÐºÐ° ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ Ð² Ð¾ÑÐ´ÐµÐ»ÑÐ½ÑÐµ ÐºÐ°Ð½Ð°Ð»Ñ, ÑÐ¾Ð¾ÑÐ²ÐµÑÑÑÐ²ÑÑÑÐ¸Ðµ Ð²ÑÐ±ÑÐ°Ð½Ð½Ð¾Ð¼Ñ Ð¿ÑÐ¸Ð½ÑÐ¸Ð¿Ñ ÑÐ¾ÑÐ¼Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ, ÑÐµÐ¿Ð»Ð¾ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¸Ðµ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÑ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ; Ð¿Ð¾Ð»Ñ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑ Ð² Ð¢ÐÐ­ÐÐ°Ñ Ð¸ ÑÐ»ÐµÐ¼ÐµÐ½ÑÐ°Ñ ÐºÐ¾Ð½ÑÑÑÑÐºÑÐ¸Ð¸ ÐÐ.
description: In this work, the design of a 600 MW nuclear power plant with VVER-600 re-actors is carried out. The choice of the NPP site was made and justified, the thermal diagram of the NPP power unit was calculated, the purpose of which was the main parameters of the NPP power unit with VVER, including the pressure and temperature of the generated steam, condensation pressure, optimal feed water temperature, and the number of heaters. In the course of calculating the thermal diagram of the NPP power unit, the costs in the element diagrams, the electrical power and the gross and net effi-ciency of the NPP were calculated. A thermohydraulic calculation of the reactor was carried out, the purpose of which was to determine the characteristics necessary for assessing the thermotechnical reliability of the core, to carry out neutronic and strength calculations of the reactor, and to select the equipment of the first circuit of the instal-lation. Thanks to it, it is possible to determine the following characteristics: the flow rate of the coolant through the reactor; distribution of flow rates along the core chan-nels; hydraulic resistances of different sections of the coolant circulation circuit, the degree of throttling of the coolant flow into separate channels corresponding to the selected principle of the core formation, thermal engineering parameters of the coolant; temperature fields in fuel rods and core structural elements.