title: ÐÐ±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð¼Ð¾Ð´ÐµÑÐ½Ð¸Ð·Ð°ÑÐ¸Ð¸ ÑÐ¸ÑÑÐµÐ¼Ñ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð³Ð¾ Ð¸ Ð¿Ð»Ð°Ð½Ð¾Ð²Ð¾Ð³Ð¾ ÑÐ°ÑÑ Ð¾Ð»Ð°Ð¶Ð¸Ð²Ð°Ð½Ð¸Ñ Ð´Ð»Ñ Ð¸ÑÑ Ð¾Ð´Ð½Ð¾Ð³Ð¾ ÑÐ¾Ð±ÑÑÐ¸Ñ Â«Ð±Ð¾Ð»ÑÑÐ°Ñ ÑÐµÑÑ 1 ÐºÐ¾Ð½ÑÑÑÐ°Â» Ñ Ð¿Ð¾Ð¼Ð¾ÑÑÑ ÐÐÐ Ð½Ð° 1 Ð±Ð»Ð¾ÐºÐµ ÐÐ°Ð»Ð¸Ð½Ð¸Ð½ÑÐºÐ¾Ð¹ 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: Justification for modernizing the emergency and planned cooling system for the initial event of a large leakage in the 1st circuit using PSA at the 1st power unit of KlnNPP
Creators: name: ÐÐ°ÑÐ¸Ð¿Ð¾Ð²Ð°, ÐÐ¸ÐºÑÐ¾Ñ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: 2023
Subjects: ÐÑÐ¾Ð¼Ð½ÑÐµ ÑÐ»ÐµÐºÑÑÐ¸ÑÐµÑÐºÐ¸Ðµ ÑÑÐ°Ð½ÑÐ¸Ð¸
Ð²ÐµÑÐ¾ÑÑÐ½Ð¾ÑÑÐ½ÑÐ¹ Ð°Ð½Ð°Ð»Ð¸Ð· Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸
ÑÐ¸ÑÑÐµÐ¼Ð° Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð³Ð¾ Ð¸ Ð¿Ð»Ð°Ð½Ð¾Ð²Ð¾Ð³Ð¾ ÑÐ°ÑÑ Ð¾Ð»Ð°Ð¶Ð¸Ð²Ð°Ð½Ð¸Ñ
Ð±Ð¾Ð»ÑÑÐ°Ñ ÑÐµÑÑ Ð¿ÐµÑÐ²Ð¾Ð³Ð¾ ÐºÐ¾Ð½ÑÑÑÐ°
probabilistic safety analysis
emergency and planned cool-down system
major leakage of the first circuit

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ñ Ð²ÐºÐ»Ð°Ð´Ð° Ð¸ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ñ Ð¼Ð¾Ð´ÐµÑÐ½Ð¸Ð·Ð°ÑÐ¸Ð¸ ÑÐ¸ÑÑÐµÐ¼Ñ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð³Ð¾ Ð¸ Ð¿Ð»Ð°Ð½Ð¾Ð²Ð¾Ð³Ð¾ ÑÐ°ÑÑÐ¾Ð»Ð°Ð¶Ð¸Ð²Ð°Ð½Ð¸Ñ Ð² Ð²ÐµÑÐ¾ÑÑÐ½Ð¾ÑÑÑ ÑÑÐ¶ÐµÐ»Ð¾Ð¹ Ð°Ð²Ð°ÑÐ¸Ð¸ (Ð¿Ð¾Ð²ÑÐµÐ¶Ð´ÐµÐ½Ð¸Ðµ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ) Ð²ÑÐ»ÐµÐ´ÑÑÐ²Ð¸Ðµ Ð¸ÑÑÐ¾Ð´Ð½Ð¾Ð³Ð¾ ÑÐ¾Ð±ÑÑÐ¸Ñ Â«ÐÐ¾Ð»ÑÑÐ°Ñ ÑÐµÑÑ Ð¿ÐµÑÐ²Ð¾Ð³Ð¾ ÐºÐ¾Ð½ÑÑÑÐ°Â». ÐÐ°Ð´Ð°ÑÐ¸, ÐºÐ¾ÑÐ¾ÑÑÐµ ÑÐµÑÐ°Ð»Ð¸ÑÑ Ð² ÑÐ¾Ð´Ðµ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ: 1) Ð¸Ð·ÑÑÐµÐ½Ð¸Ðµ Ð¼ÐµÑÐ¾Ð´Ð¾Ð² ÐÐÐ; 2) Ð¸Ð·ÑÑÐµÐ½Ð¸Ðµ ÑÐ¸ÑÑÐµÐ¼Ñ Ð¸ ÐµÐµ ÑÐ»ÐµÐ¼ÐµÐ½ÑÐ¾Ð², Ð²Ð»Ð¸ÑÑÑÐ¸Ñ Ð½Ð° Ð±ÐµÐ·Ð¾ÑÐºÐ°Ð·Ð½Ð¾ÑÑÑ Ð¸ ÑÐ°Ð±Ð¾ÑÐ¾ÑÐ¿Ð¾ÑÐ¾Ð±Ð½Ð¾ÑÑÑ ÑÐ¸ÑÑÐµÐ¼Ñ; 3) ÑÐ±Ð¾Ñ Ð´Ð°Ð½Ð½ÑÑ Ð´Ð»Ñ ÑÐ°ÑÑÐµÑÐ° Ð¸ Ð¿Ð¾ÑÑÑÐ¾ÐµÐ½Ð¸Ðµ Ð»Ð¾Ð³Ð¸ÐºÐ¾-Ð²ÐµÑÐ¾ÑÑÐ½Ð¾ÑÑÐ½ÑÑ Ð¼Ð¾Ð´ÐµÐ»ÐµÐ¹; 4) Ð°Ð½Ð°Ð»Ð¸Ð· Ð¿Ð¾Ð»ÑÑÐµÐ½Ð½ÑÑ Ð² ÑÐ¾Ð´Ðµ ÑÐ°ÑÑÐµÑÐ° Ð´Ð°Ð½Ð½ÑÑ. Ð Ð°Ð±Ð¾ÑÐ° Ð²ÑÐ¿Ð¾Ð»Ð½ÐµÐ½Ð° Ñ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·Ð¾Ð²Ð°Ð½Ð¸ÐµÐ¼ ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¾Ð¹ Ð¸ ÑÐºÑÐ¿Ð»ÑÐ°ÑÐ°ÑÐ¸Ð¾Ð½Ð½Ð¾Ð¹ Ð´Ð¾ÐºÑÐ¼ÐµÐ½ÑÐ°ÑÐ¸Ð¸, Ð±Ð°Ð· Ð´Ð°Ð½Ð½ÑÑ Ð¿Ð¾ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸, Ð°Ð»ÑÐ±Ð¾Ð¼Ð¾Ð² ÑÑÐµÐ¼ ÑÐ¸ÑÑÐµÐ¼ ÑÐµÐ°ÐºÑÐ¾ÑÐ½Ð¾Ð³Ð¾ ÑÐµÑÐ°. ÐÑÐ»Ð¸ ÑÑÐ°Ð²Ð½ÐµÐ½Ñ Ð´Ð²Ðµ ÑÐµÑÐ½Ð¾Ð»Ð¾Ð³Ð¸ÑÐµÑÐºÐ¸Ðµ ÑÑÐµÐ¼Ñ: Ð´Ð¾ Ð¸ Ð¿Ð¾ÑÐ»Ðµ Ð¼Ð¾Ð´ÐµÑÐ½Ð¸Ð·Ð°ÑÐ¸Ð¸, Ð´Ð»Ñ ÐºÐ°Ð¶Ð´Ð¾Ð¹ Ð¿Ð¾ÑÑÐ¸ÑÐ°Ð½Ð° Ð²ÐµÑÐ¾ÑÑÐ½Ð¾ÑÑÑ Ð¾ÑÐºÐ°Ð·Ð° ÑÐ¸ÑÑÐµÐ¼Ñ, Ð¸ Ð²ÐºÐ»Ð°Ð´ ÑÑÐ¾Ð³Ð¾ Ð¾ÑÐºÐ°Ð·Ð° Ð² Ð²ÐµÑÐ¾ÑÑÐ½Ð¾ÑÑÑ Ð½Ð°ÑÑÑÐ¿Ð»ÐµÐ½Ð¸Ñ ÑÑÐ¶ÐµÐ»Ð¾Ð¹ Ð°Ð²Ð°ÑÐ¸Ð¸ (ÐÐ¢Ð) Ñ Ð¿Ð¾Ð²ÑÐµÐ¶Ð´ÐµÐ½Ð¸ÐµÐ¼ Ð°ÐºÑÐ¸Ð²Ð½Ð¾Ð¹ Ð·Ð¾Ð½Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ°. ÐÐ½Ð°Ð»Ð¸Ð· Ð¿ÑÐ¾Ð²Ð¾Ð´Ð¸Ð»ÑÑ Ð¼ÐµÑÐ¾Ð´Ð¾Ð¼ Ð²ÐµÑÐ¾ÑÑÐ½Ð¾ÑÑÐ½Ð¾Ð³Ð¾ Ð°Ð½Ð°Ð»Ð¸Ð·Ð° Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ â Ð¿Ð¾ÑÑÑÐ¾ÐµÐ½Ð¸ÐµÐ¼ Ð»Ð¾Ð³Ð¸ÐºÐ¾-Ð²ÐµÑÐ¾ÑÑÐ½Ð¾ÑÑÐ½ÑÑ Ð¼Ð¾Ð´ÐµÐ»ÐµÐ¹ Ñ Ð¿Ð¾Ð¼Ð¾ÑÑÑ Ð´ÐµÑÐµÐ²ÑÐµÐ² Ð¾ÑÐºÐ°Ð·Ð¾Ð² Ð² Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ðµ FTA Top Event. Ð ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ Ð±ÑÐ»Ð¸ Ð¿ÑÐ¾Ð°Ð½Ð°Ð»Ð¸Ð·Ð¸ÑÐ¾Ð²Ð°Ð½Ñ Ð¼Ð¾Ð´ÐµÑÐ½Ð¸Ð·Ð°ÑÐ¸Ñ ÑÐ¸ÑÑÐµÐ¼Ñ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð³Ð¾ Ð¸ Ð¿Ð»Ð°Ð½Ð¾Ð²Ð¾Ð³Ð¾ ÑÐ°ÑÑÐ¾Ð»Ð°Ð¶Ð¸Ð²Ð°Ð½Ð¸Ñ Ð¸ ÑÐ°ÑÑÐµÑÑ Ð²ÐºÐ»Ð°Ð´Ð° Ð¾ÑÐºÐ°Ð·Ð° ÑÐ¸ÑÑÐµÐ¼Ñ Ð´Ð¾ Ð¸ Ð¿Ð¾ÑÐ»Ðµ Ð¼Ð¾Ð´ÐµÑÐ½Ð¸Ð·Ð°ÑÐ¸Ð¸ Ð² ÐÐ¢Ð.
description: This work is devoted to determining the contribution and justification of the modernization of the emergency and planned cooldown system to the probability of a severe accident (core melting) due to the initiating event âLarge leakage of the 1st circuit.â Problems that were solved during the study: 1) study of PSA methods; 2) study and description of the system and its elements that affect the safety and performance of the system; 3) collection of data for calculations and construction of logical-probabilistic models; 4) analysis of the data obtained during the calculation. The work was carried out using technical and operational documentation, reliability databases, and albums of diagrams of reactor shop systems. Two technological schemes were compared: before and after modernization, for each the probability of system failure was calculated, and the contribution of this failure to the probability of a severe accident with damage to the reactor core. The analysis was carried out using the method of probabilistic safety analysis - the construction of logical and probabilistic models using fault trees in the FTA Top Event program. As a result, the modernization of the emergency and planned cooling system and calculations of the contribution of system failure before and after modernization in the probability of severe accident were analyzed.