title: ÐÑÐ±Ð¾Ñ Ð¸ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð¾ÑÐ½Ð¾Ð²Ð½ÑÑ Ñ Ð°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸Ðº ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ¾Ð¼ ÐÐÐ­Ð -Ð¡ÐÐ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¾Ð¹ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑÑ 1200 ÐÐÑ
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð±Ð°ÐºÐ°Ð»Ð°Ð²ÑÐ°
titleType: Subtitle
title: Selection and justification of the main characteristics of a power unit with a VVER-SKD reactor with an electrical power of 1200 MW
Creators: name: Ð¦Ð°ÑÐµÐ², 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: 2023
Subjects: ÐÐÐ­Ð Ð¡ÐÐ
ÑÐµÐ¿Ð»Ð¾Ð²Ð°Ñ ÑÑ ÐµÐ¼Ð° ÐÐ­Ð¡ ÐÐÐ­Ð Ð¡ÐÐ
ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÐ°ÑÑÐµÑ ÐÐÐ­Ð Ð¡ÐÐ
Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ ÐÐÐ­Ð Ð¡ÐÐ
VVER SKD
thermal scheme of VVER SKD NPP
thermal calculation of VVER SKD
hydraulic calculation of VVER SKD

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° ÑÐ°ÑÑÐµÑÑ ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÑÐµÐ¼Ñ ÐÐ­Ð¡ Ñ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ¾Ð¼ 4 Ð¿Ð¾ÐºÐ¾Ð»ÐµÐ½Ð¸Ñ ÐÐÐ­Ð -Ð¡ÐÐ 1200 ÐÐÑ Ð¸ ÑÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¾Ð¼Ñ ÑÐ°ÑÑÐµÑÑ ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÐÐÐ­Ð  Ñ ÑÐ²ÐµÑÑÐºÑÐ¸ÑÐ¸ÑÐµÑÐºÐ¸Ð¼ Ð´Ð°Ð²Ð»ÐµÐ½Ð¸ÐµÐ¼ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ. ÐÐ°Ð´Ð°ÑÐ¸, ÐºÐ¾ÑÐ¾ÑÑÐµ ÑÐµÑÐ°Ð»Ð¸ÑÑ Ð² ÑÐ¾Ð´Ðµ Ð²ÑÐ¿Ð¾Ð»Ð½ÐµÐ½Ð¸Ñ ÑÐ°Ð±Ð¾ÑÑ: 1. ÐÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð¸ ÑÐ°ÑÑÐµÑ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÐ¾Ð² ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÑÐµÐ¼Ñ ÐÐ­Ð¡ Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ¾Ð¼ ÐÐÐ­Ð -Ð¡ÐÐ Ð½Ð° Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ð¸ ÑÐµÑÐµÑÐµÐ½ÑÐ½Ð¾Ð³Ð¾ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° Ñ ÑÑÑÐ±Ð¸Ð½Ð¾Ð¹ Ð-1200-240. 2. ÐÐ±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð¢ÐÐ­Ð Ð¾Ñ Ð¿Ð»Ð°Ð²Ð»ÐµÐ½Ð¸Ñ 3. ÐÐ½Ð°Ð»Ð¸Ð· Ð¿Ð¾Ð»ÑÑÐµÐ½Ð½ÑÑ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ¾Ð² Ð Ð°Ð±Ð¾ÑÐ° Ð¿ÑÐ¾Ð²Ð¾Ð´Ð¸Ð»Ð°ÑÑ Ð½Ð° Ð½Ð°ÑÑÐ½Ð¾Ð¹ Ð±Ð°Ð·Ðµ Ð¤ÐÐ£Ð âÐÐÐ¢Ðâ, Ð³Ð´Ðµ ÑÐ¾Ð±Ð¸ÑÐ°Ð»Ð°ÑÑ Ð¸Ð½ÑÐ¾ÑÐ¼Ð°ÑÐ¸Ñ Ð¾ ÑÐµÑÐ½Ð¾Ð»Ð¾Ð³Ð¸Ð¸ Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ, ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ°Ð»ÑÐ½ÑÑ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸ÐºÐ°Ñ ÐÐ ÐÐÐ­Ð  Ð¡ÐÐ. ÐÑÐµÐ´Ð¾ÑÑÐ°Ð²Ð»ÑÐ»ÑÑ Ð´Ð¾ÑÑÑÐ¿ Ðº Ð½Ð°ÑÑÐ½Ð¾Ð¹ Ð±Ð°Ð·Ðµ Ð¸ Ð»Ð¸ÑÐµÑÐ°ÑÑÑÐµ Ð¿ÑÐµÐ´Ð¿ÑÐ¸ÑÑÐ¸Ñ. Ð Ð°ÑÑÐµÑ Ð¿ÑÐ¾Ð²Ð¾Ð´Ð¸Ð»ÑÑ Ñ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·Ð¾Ð²Ð°Ð½Ð¸ÐµÐ¼ Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ð½Ð¾Ð³Ð¾ Ð¾Ð±ÐµÑÐ¿ÐµÑÐµÐ½Ð¸Ñ Microsoft Excel Ð¸ Mathcad. Ð ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ ÑÐ°Ð±Ð¾ÑÑ ÑÐ¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð° ÑÐµÐ¿Ð»Ð¾Ð²Ð°Ñ ÑÑÐµÐ¼Ð° ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ° ÐÐ­Ð¡ Ñ ÐÐÐ­Ð -Ð¡ÐÐ, Ð¿ÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÐµÐ½ ÑÐ°ÑÑÐµÑ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÐ¾Ð² ÑÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÑÐµÐ¼Ñ Ð¸ Ð¾ÑÐµÐ½ÐºÐ° ÐÐÐ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ°. ÐÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÐµÐ½ ÑÐ°ÑÑÐµÑ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÑ ÑÑÐµÐ½ÐºÐ¸ Ð¢ÐÐ­Ð, ÑÐµÐ½ÑÑÐ° ÑÐ¾Ð¿Ð»Ð¸Ð²Ð½Ð¾Ð¹ ÑÐ°Ð±Ð»ÐµÑÐºÐ¸ Ð´Ð»Ñ ÑÐ°Ð¼Ð¾Ð¹ ÑÐ½ÐµÑÐ³Ð¾Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð½Ð¾Ð¹ Ð¢ÐÐ¡, Ð° ÑÐ°ÐºÐ¶Ðµ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ Ð½Ð° Ð¿Ð¾Ð´ÑÐµÐ¼Ð½Ð¾Ð¼ Ð¸ Ð¾Ð¿ÑÑÐºÐ½Ð¾Ð¼ ÑÑÐ°ÑÑÐºÐµ Ð´Ð²ÑÑÑÐ¾Ð´Ð¾Ð²Ð¾Ð¹ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°, ÑÐ´ÐµÐ»Ð°Ð½Ñ Ð²ÑÐ²Ð¾Ð´Ð° Ð¾ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð¸ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ ÑÐ¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð½Ð¾Ð³Ð¾ ÑÐµÐ°ÐºÑÐ¾ÑÐ°. ÐÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÐµÐ½ Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ°ÑÑÐµÑ Ð´Ð»Ñ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ñ Ð¿Ð¾ÑÐµÑÑ Ð´Ð°Ð²Ð»ÐµÐ½Ð¸Ñ Ð² ÐÐ, Ð¸ Ð¿ÑÐ¾Ð¸Ð·Ð²ÐµÐ´ÐµÐ½Ð¾ ÑÑÐ°Ð²Ð½ÐµÐ½Ð¸Ðµ Ð¿Ð¾Ð»ÑÑÐµÐ½Ð½ÑÑ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ¾Ð² Ñ Ð¿Ð¾ÑÐµÑÑÐ¼Ð¸ Ð² ÐÐÐ­Ð -1200.
description: This work is dedicated to the calculation of the thermal scheme of a nuclear power plant (NPP) with a 4th generation VVER-SKD 1200 MW reactor and the thermo-hydraulic calculation of the VVER reactor with supercritical coolant pressure. The research set the following goals: 1. Designing and calculating the parameters of the thermal scheme of a nuclear power plant (NPP) with a VVER-SKD reactor based on a reference power unit with a K-1200-240 turbine. 2. Justification of the reliability of the fuel rod element against melting. 3. Analysis of the obtained results. The work was carried out at the scientific base of the Federal State Unitary Enterprise "NITI," where information on the design technology and experimental characteristics of the VVER SKD core was gathered. Access to the scientific database and literature of the enterprise was provided. The calculations were performed using Microsoft Excel and Mathcad software. As a result of the work, the thermal scheme of the NPP power unit with VVER-SKD was designed, the parameters of the thermal scheme were calculated and the efficiency of the power unit was estimated. The calculation of the temperature of the fuel rod cladding, the center of the fuel pellet for the most power-intensive fuel assembly, as well as the coolant temperature in the ascending and descending sections of the two-pass active zone of the reactor, has been performed. Conclusions have been drawn regarding the reliability and safety of the designed reactor. A hydraulic calculation was performed to determine the pressure losses in the core, and a comparison was made between the obtained results and the losses in the VVER-1200.