title: Ð¢ÐµÐ¿Ð»Ð¾Ð²Ð¾Ð¹ ÑÐ°ÑÑÐµÑ Ð¿Ð¾ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ñ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ ÑÑÑÐ°Ð½Ð¾Ð²ÐºÐ¸ Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ¾Ð¼ ÐÐÐ­Ð -1200 Ñ Ð¾Ð±ÐµÑÑÐ¾ÑÐ¸Ð²Ð°Ð½Ð¸ÐµÐ¼ ÐÐ­Ð¡
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: Thermal analysis for safety justification of nuclear power systems with WWER-1200 in case of station blackout
Creators: name: Ð¡ÐµÐ¼Ð¸ÐºÐ¾Ð², ÐÑÐ»Ð°Ñ
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: 2022
Subjects: ÐÑÐ¾Ð¼Ð½ÑÐµ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¸Ðµ ÑÑÐ°Ð½ÑÐ¸Ð¸
Ð¯Ð´ÐµÑÐ½ÑÐµ ÑÐµÐ°ÐºÑÐ¾ÑÑ
ÑÐ¸ÑÑÐµÐ¼Ð° Ð¿Ð°ÑÑÐ¸Ð²Ð½Ð¾Ð³Ð¾ Ð¾ÑÐ²Ð¾Ð´Ð° ÑÐµÐ¿Ð»Ð°
Ð¾ÑÑÐ°ÑÐ¾ÑÐ½Ð¾Ðµ ÑÐµÐ¿Ð»Ð¾Ð²ÑÐ´ÐµÐ»ÐµÐ½Ð¸Ðµ
Ð°ÐºÑÐ¸Ð²Ð½Ð°Ñ Ð·Ð¾Ð½Ð°
system passive heat removal system
recovery heat
core

description: Ð¢ÐµÐ¼Ð° Ð²ÑÐ¿ÑÑÐºÐ½Ð¾Ð¹ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÑ: Â«Ð¢ÐµÐ¿Ð»Ð¾Ð²ÑÐ¹ ÑÐ°ÑÑÐµÑ Ð¿Ð¾ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ñ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ ÑÑÑÐ°Ð½Ð¾Ð²ÐºÐ¸ Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ¾Ð¼ ÐÐÐ­Ð -1200 Ñ Ð¾Ð±ÐµÑÑÐ¾ÑÐ¸Ð²Ð°Ð½Ð¸ÐµÐ¼ ÐÐ­Ð¡Â».ÐÐ°Ð´Ð°ÑÐ¸, ÑÐµÑÐ°ÐµÐ¼ÑÐµ Ð² ÑÐ¾Ð´Ðµ ÑÐ°Ð±Ð¾ÑÑ: Ð ÑÐ°Ð±Ð¾ÑÐµ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ñ Ð³ÐµÐ¾Ð¼ÐµÑÑÐ¸ÑÐµÑÐºÐ¸Ðµ Ð¸ ÑÐµÐ¿Ð»Ð¾Ð³Ð¸Ð´ÑÐ°Ð²Ð»Ð¸ÑÐµÑÐºÐ¸Ðµ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸ÐºÐ¸ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÑÐ¸Ð¿Ð° ÐÐÐ­Ð  Ð¿ÑÐ¸ Ð½Ð¾ÑÐ¼Ð°Ð»ÑÐ½Ð¾Ð¹ ÑÐºÑÐ¿Ð»ÑÐ°ÑÐ°ÑÐ¸Ð¸. Ð Ð°ÑÑÐ¼Ð¾ÑÑÐµÐ½Ð° ÑÐ¸ÑÑÐµÐ¼Ð° Ð¿Ð°ÑÑÐ¸Ð²Ð½Ð¾Ð³Ð¾ Ð¾ÑÐ²Ð¾Ð´Ð° Ð¾ÑÑÐ°ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐµÐ¿Ð»Ð¾Ð²ÑÐ´ÐµÐ»ÐµÐ½Ð¸Ñ, Ð¿ÑÐ¾Ð°Ð½Ð°Ð»Ð¸Ð·Ð¸ÑÐ¾Ð²Ð°Ð½Ð° ÑÐ°Ð±Ð¾ÑÐ° ÑÐ¸ÑÑÐµÐ¼Ñ Ð¿ÑÐ¸ Ð°Ð²Ð°ÑÐ¸ÑÑ, ÑÐ²ÑÐ·Ð°Ð½Ð½ÑÑ Ñ Ð¾Ð±ÐµÑÑÐ¾ÑÐ¸Ð²Ð°Ð½Ð¸ÐµÐ¼ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐ°. Ð Ð°ÑÑÐ¼Ð¾ÑÑÐµÐ½ ÑÑÐµÐ½Ð°ÑÐ¸Ð¹ Ð°Ð²Ð°ÑÐ¸Ð¸ Ð¿ÑÐ¸ Ð¿Ð¾Ð»Ð½Ð¾Ð¹ Ð¿Ð¾ÑÐµÑÐµ ÑÐ»ÐµÐºÑÑÐ¾ÑÐ½Ð°Ð±Ð¶ÐµÐ½Ð¸Ñ ÑÑÐ°Ð½ÑÐ¸Ð¸. ÐÐ½Ð°Ð»Ð¸ÑÐ¸ÑÐµÑÐºÐ¸Ð¼ Ð¸ ÑÐ¸ÑÐ»ÐµÐ½Ð½ÑÐ¼ Ð¼ÐµÑÐ¾Ð´Ð°Ð¼Ð¸ ÑÐ°ÑÑÑÐ¸ÑÐ°Ð½Ñ Ð´Ð»Ñ ÑÐ°Ð·Ð½Ð¾Ð³Ð¾ Ð¼Ð¾Ð¼ÐµÐ½ÑÐ° Ð²ÑÐµÐ¼ÐµÐ½Ð¸ Ð¼Ð¾ÑÐ½Ð¾ÑÑÑ Ð¾ÑÑÐ°ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐµÐ¿Ð»Ð¾Ð²ÑÐ´ÐµÐ»ÐµÐ½Ð¸Ñ, ÑÐµÐ¶Ð¸Ð¼Ñ ÑÐµÑÐµÐ½Ð¸Ñ ÑÐµÐ¿Ð»Ð¾Ð½Ð¾ÑÐ¸ÑÐµÐ»Ñ Ð¸ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑÐ½ÑÐµ Ð¿Ð¾Ð»Ñ Ð¿Ð¾ Ð²ÑÑÐ¾ÑÐµ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°. ÐÑÐ¾Ð³Ð¾Ð¼ ÑÐ°Ð±Ð¾ÑÑ ÑÑÐ°Ð»Ð¾ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ð¿ÑÐ¸ ÑÑÐ»Ð¾Ð²Ð¸Ð¸ Ð½Ð¾ÑÐ¼Ð°Ð»ÑÐ½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÑ ÑÐ¸ÑÑÐµÐ¼Ñ Ð¿Ð°ÑÑÐ¸Ð²Ð½Ð¾Ð³Ð¾ ÑÐµÐ¿Ð»Ð¾Ð¾ÑÐ²Ð¾Ð´Ð° Ñ ÑÐ¾ÑÐºÐ¸ Ð·ÑÐµÐ½Ð¸Ñ Ð·Ð°Ð¿Ð°ÑÐ° Ð´Ð¾ ÐºÑÐ¸Ð·Ð¸ÑÐ° ÑÐµÐ¿Ð»Ð¾Ð¾Ð±Ð¼ÐµÐ½Ð° Ð¸ Ð´Ð¾Ð¿ÑÑÑÐ¸Ð¼ÑÑ ÑÐµÐ¼Ð¿ÐµÑÐ°ÑÑÑ ÑÐ¾Ð¿Ð»Ð¸Ð²Ð° Ð¸ Ð¾Ð±Ð¾Ð»Ð¾ÑÐºÐ¸, Ð¾Ð±ÐµÑÐ¿ÐµÑÐ¸Ð²Ð°ÑÑÐ¸Ñ Ð³ÐµÑÐ¼ÐµÑÐ¸ÑÐ½Ð¾ÑÑÑ ÑÐµÐ¿Ð»Ð¾Ð²ÑÐ´ÐµÐ»ÑÑÑÐ¸Ñ ÑÐ»ÐµÐ¼ÐµÐ½ÑÐ¾Ð², ÑÑÐ¾ Ð¾Ð±ÐµÑÐ¿ÐµÑÐ¸Ð²Ð°ÐµÑ ÑÐ°Ð´Ð¸Ð°ÑÐ¸Ð¾Ð½Ð½ÑÑ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÑ.
description: Topic of the final qualification work: "Thermal calculation for the safety justification of the installation with the VVER-1200 reactor with NPP de-energization". Tasks solved in the course of work:Geometric and thermal-hydraulic characteristics of the active zone of a VVER-type reactor during normal operation have been studied. The system of passive removal of residual heat is considered, the operation of the system is analyzed in case of accidents associated with a blackout of the power unit. The scenario of an accident with a complete loss of power supply to the station is considered. Analytical and numerical methods are used to calculate the power of residual heat release, coolant flow regimes and temperature fields along the height of the reactor core for different points in time. The result of the work was the substantiation of the reliability of the reactor core under the condition of normal operation of the passive heat removal system in terms of the reserve before the heat transfer crisis and the allowable temperatures of the fuel and cladding, which ensure the tightness of the fuel elements, which ensures radiation safety.