title: ÐÑÐ¾ÐµÐºÑ ÐÐ­Ð¡ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑÑ 1500 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: 1,500 MW Nuclear Power plant project in the province of KÄ±rklareli, Turkey
Creators: name: ÐÑÐ°, Ð¡ÑÑÐµÐ¹Ð»
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 -1500
ÐÐ­Ð¡
Ð³ÐµÐ¾Ð¼ÐµÑÑÐ¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ
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-1500 reactor
NPP
neutron-physical caculation
geometric calculation
thermohydraulic calculation
thermal scheme
turkish electricity

description: Ð¦ÐµÐ»ÑÑ Ð´Ð°Ð½Ð½Ð¾Ð³Ð¾ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÑÐ²Ð»ÑÐµÑÑÑ Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ ÐÐ­Ð¡ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑÑ 1500 ÐÐÑ Ð² Ð¿ÑÐ¾Ð²Ð¸Ð½ÑÐ¸Ð¸ ÐÑÑÐºÐ»Ð°ÑÐµÐ»Ð¸. Ð Ð´Ð°Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÐµ Ð±ÑÐ» ÑÐ°Ð·ÑÐ°Ð±Ð¾ÑÐ°Ð½ Ð¿ÑÐ¾ÐµÐºÑ Ð°ÑÐ¾Ð¼Ð½Ð¾Ð¹ ÑÐ»ÐµÐºÑÑÐ¾ÑÑÐ°Ð½ÑÐ¸Ð¸ (ÐÐ­Ð¡) Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°Ð¼Ð¸ ÑÐ¸Ð¿Ð° ÐÐÐ­Ð  Ð¼Ð¾ÑÐ½Ð¾ÑÑÑÑ 1500 ÐÐÑ. ÐÑÐ»Ð¸ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ñ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ Ð¸ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½ Ð²ÑÐ±Ð¾Ñ Ð¼ÐµÑÑÐ° Ð´Ð»Ñ ÑÐ°Ð·Ð¼ÐµÑÐµÐ½Ð¸Ñ ÐÐ­Ð¡, Ð° ÑÐ°ÐºÐ¶Ðµ Ð²ÑÐ¿Ð¾Ð»Ð½ÐµÐ½ ÑÐ°ÑÑÐµÑ ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÑÐµÐ¼Ñ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° ÑÑÐ°Ð½ÑÐ¸Ð¸. Ð¦ÐµÐ»ÑÑ Ð´Ð°Ð½Ð½Ð¾Ð³Ð¾ ÑÐ°ÑÑÐµÑÐ° ÑÐ²Ð»ÑÐ»Ð¾ÑÑ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ Ð¿Ð¾ÐºÐ°Ð·Ð°ÑÐµÐ»ÐµÐ¹ ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÐºÐ¾Ð½Ð¾Ð¼Ð¸ÑÐ½Ð¾ÑÑÐ¸ Ð¸ ÑÐµÑÐ¼Ð¾Ð´Ð¸Ð½Ð°Ð¼Ð¸ÑÐµÑÐºÐ¸Ñ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÐ¾Ð², Ð° ÑÐ°ÐºÐ¶Ðµ ÑÐ°ÑÑÐ¾Ð´Ð° ÑÐ°Ð±Ð¾ÑÐµÐ³Ð¾ ÑÐµÐ»Ð° ÑÐµÑÐµÐ· Ð²ÑÐµ ÑÐ»ÐµÐ¼ÐµÐ½ÑÑ ÑÑÐµÐ¼Ñ (ÑÑÑÐ±Ð¸Ð½Ð½ÑÐµ ÑÐµÐºÑÐ¸Ð¸, ÑÐµÐ¿Ð»Ð¾Ð¾Ð±Ð¼ÐµÐ½Ð½Ð¸ÐºÐ¸, Ð½Ð°ÑÐ¾ÑÑ, ÑÐ¶ÐµÐºÑÐ¾ÑÑ Ð¸ Ð´Ñ.), Ð²ÐºÐ»ÑÑÐ°Ñ ÑÐµÐ³ÐµÐ½ÐµÑÐ°ÑÐ¸Ð²Ð½ÑÐµ Ð¸ ÑÐµÑÐµÐ²ÑÐµ Ð¿Ð¾Ð´Ð¾Ð³ÑÐµÐ²Ð°ÑÐµÐ»Ð¸. Ð¢Ð°ÐºÐ¶Ðµ Ð¾Ñ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°, Ð½Ð°Ð¿ÑÐ°Ð²Ð»ÐµÐ½Ð½ÑÐ¹ Ð½Ð° 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Ð°Ð¼ÐºÐ°Ñ ÑÐ°Ð±Ð¾ÑÑ Ð²ÑÐ¿Ð¾Ð»Ð½ÐµÐ½Ñ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ðµ Ð¸ Ð¿ÑÐ¾ÑÐ½Ð¾ÑÑÐ½ÑÐµ ÑÐ°ÑÑÐµÑÑ ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ð¸ Ð¿ÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÐµÐ½ Ð²ÑÐ±Ð¾Ñ Ð¾Ð±Ð¾ÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ Ð´Ð»Ñ Ð¿ÐµÑÐ²Ð¾Ð³Ð¾ ÐºÐ¾Ð½ÑÑÑÐ° ÑÑÑÐ°Ð½Ð¾Ð²ÐºÐ¸. Ð­ÑÐ¸ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ Ð¿Ð¾Ð·Ð²Ð¾Ð»Ð¸Ð»Ð¸ 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 Ð¿Ð¾ÑÐ¾ÐºÐ¾Ð² 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 ÑÐ¸ÑÐºÑÐ»ÑÑÐ¸Ð¾Ð½Ð½Ð¾Ð³Ð¾ ÐºÐ¾Ð½ÑÑÑ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; ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÐ½ÑÐµ Ð¿Ð¾Ð»Ñ Ð² ÑÐµÐ¿Ð»Ð¾Ð²ÑÐ´ÐµÐ»ÑÑÑÐ¸Ñ ÑÐ»ÐµÐ¼ÐµÐ½ÑÐ°Ñ Ð¸ ÐºÐ¾Ð½ÑÑÑÑÐºÑÐ¸Ð²Ð½ÑÑ ÑÐ»ÐµÐ¼ÐµÐ½ÑÐ°Ñ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ.
description: The purpose of this study is to design a 1500 MW nuclear power plant in the province of KÄ±rklareli. In this work, a project of a nuclear power plant (NPP) with VVER-type reactors with a capacity of 1500 MW has been developed. The selection of a site for NPP construction was made and justified, and the thermal scheme of the power unit of the plant was calculated. The main purpose of this calculation was to determine thermal efficiency indicators, as well as thermodynamic parameters and values of working body flows through all elements of the scheme, such as turbine sections, heat exchangers, pumps, ejectors and other components, including regenerative and network heaters. A thermal-hydraulic calculation of the reactor was also performed to determine the characteristics required to assess the thermal reliability of the core. In addition, neutron-physical and strength calculations of the reactor were performed and the selection of equipment for the first circuit of the plant was made. As a result, the following characteristics were determined: coolant flow rate through the reactor, flow distribution through the core channels, hydraulic resistances of different sections of the coolant circulation circuit, the degree of throttling of the coolant flow into individual channels (in accordance with the selected core formation principle), coolant thermal parameters, and temperature fields in fuel elements and core structural elements.