title: ÐÐ±ÐµÑÐ¿ÐµÑÐµÐ½Ð¸Ðµ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð¸ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ Ð¾Ð±Ð¾ÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ Ð°ÑÐ¾Ð¼Ð½ÑÑ ÑÐ»ÐµÐºÑÑÐ¾ÑÑÐ°Ð½ÑÐ¸Ð¹ Ñ Ð¿Ð¾Ð¼Ð¾ÑÑÑ Ð²ÐµÑÐ¾ÑÑÐ½Ð¾ÑÑÐ½Ð¾Ð³Ð¾ Ð°Ð½Ð°Ð»Ð¸Ð·Ð° Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸
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: Ensuring reliability and safety of nuclear power plant equipment via probablistic safety analysis
Creators: name: Ð£ÑÐ»Ñ, ÐÑÑÐ°Ð½
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¸
Ð¯Ð´ÐµÑÐ½ÑÐµ ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÑÐµÑÐºÐ¸Ðµ ÑÑÑÐ°Ð½Ð¾Ð²ÐºÐ¸
ÐÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÑ Ð¶Ð¸Ð·Ð½ÐµÐ´ÐµÑÑÐµÐ»ÑÐ½Ð¾ÑÑÐ¸ ÑÐµÐ»Ð¾Ð²ÐµÐºÐ°
Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÑ
Ð´ÐµÑÐµÐ²Ð¾ Ð¾ÑÐºÐ°Ð·Ð¾Ð²
reliability
fault tree

description: Ð¡Ð Ð ÑÐ²Ð»ÑÐµÑÑÑ ÑÑÐ½Ð´Ð°Ð¼ÐµÐ½ÑÐ°Ð»ÑÐ½Ð¾Ð¹ ÑÐ°ÑÑÑÑ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ ÑÐ´ÐµÑÐ½ÑÑ ÑÐµÐ°ÐºÑÐ¾ÑÐ¾Ð² Ð¾Ñ Ð¿ÑÐ¾ÐµÐºÑÐ¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð´Ð¾ Ð²ÑÐ²Ð¾Ð´Ð° Ð¸Ð· ÑÐºÑÐ¿Ð»ÑÐ°ÑÐ°ÑÐ¸Ð¸. ÐÐ¿ÐµÑÐ²ÑÐµ ÐµÐ³Ð¾ Ð²Ð°Ð¶Ð½Ð¾ÑÑÑ Ð±ÑÐ»Ð° Ð¾ÑÐ¾Ð·Ð½Ð°Ð½Ð° Ð¿Ð¾ÑÐ»Ðµ Ð°Ð²Ð°ÑÐ¸Ð¸ Ð½Ð° Ð²ÑÐ¾ÑÐ¾Ð¼ ÑÐ½ÐµÑÐ³Ð¾Ð±Ð»Ð¾ÐºÐµ Ð¢ÑÐ¸-ÐÐ°Ð¹Ð»-ÐÐ¹Ð»ÐµÐ½Ð´Ð°. ÐÐ¾ÑÐ»Ðµ Ð°Ð²Ð°ÑÐ¸Ð¸ Ð½Ð° ÐÐ­Ð¡ "Ð¤ÑÐºÑÑÐ¸Ð¼Ð°-1" ÑÑÐ°Ð»Ð¾ Ð¿Ð¾Ð½ÑÑÐ½Ð¾, ÑÑÐ¾ Ð°Ð½Ð°Ð»Ð¸Ð· ÑÐ´ÐµÑÐ½Ð¾Ð¹ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ Ð²Ð°Ð¶ÐµÐ½ Ð´Ð»Ñ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾Ð¹ ÑÐºÑÐ¿Ð»ÑÐ°ÑÐ°ÑÐ¸Ð¸. Ð Ð´Ð°Ð½Ð½Ð¾Ð¼ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ð¸ Ð°Ð½Ð°Ð»Ð¸Ð· Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ Ð¸ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð²ÑÐ¿Ð¾Ð»Ð½ÐµÐ½ Ð´Ð»Ñ Ð»Ð°Ð±Ð¾ÑÐ°ÑÐ¾ÑÐ½Ð¾Ð¹ ÑÑÑÐ°Ð½Ð¾Ð²ÐºÐ¸, ÑÐ°ÑÐ¿Ð¾Ð»Ð¾Ð¶ÐµÐ½Ð½Ð¾Ð¹ Ð² Ð½Ð°ÑÑÐ½Ð¾-Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°ÑÐµÐ»ÑÑÐºÐ¾Ð¼ ÑÐµÐ½ÑÑÐµ ÐÐ±Ð½Ð¸Ð½ÑÐºÐ¾Ð³Ð¾ Ð¸Ð½ÑÑÐ¸ÑÑÑÐ° Ð°ÑÐ¾Ð¼Ð½Ð¾Ð¹ ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÐºÐ¸ ÐÐÐ¤Ð Ð² ÐÐ±Ð½Ð¸Ð½ÑÐºÐµ, Ð Ð¾ÑÑÐ¸Ñ. ÐÐ°Ð±Ð¾ÑÐ°ÑÐ¾ÑÐ¸Ñ Ð¿ÑÐµÐ´ÑÑÐ°Ð²Ð»ÑÐµÑ ÑÐ¾Ð±Ð¾Ð¹ ÐºÐ¾Ð½ÑÑÑÑÐºÑÐ¸Ñ Ð¼Ð¾Ð´ÐµÐ»Ð¸ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°ÑÐµÐ»ÑÑÐºÐ¾Ð³Ð¾ ÑÐµÐ°ÐºÑÐ¾ÑÐ° Ð¸ Ð¿ÑÐ¸Ð·Ð²Ð°Ð½Ð° Ð¿Ð¾Ð½ÑÑÑ Ð¾Ð±ÐµÑÐ¿ÐµÑÐµÐ½Ð¸Ðµ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð¸ Ð±ÐµÐ·Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸ Ñ Ð¿Ð¾Ð¼Ð¾ÑÑÑ Ð¡Ð Ð Ð´Ð»Ñ Ð¾Ð±Ð¾ÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÐÐ­Ð¡. ÐÐ°Ð´ÐµÐ¶Ð½Ð¾ÑÑÑ Ð¸ Ð²ÐµÑÐ¾ÑÑÐ½Ð¾ÑÑÑ Ð±ÐµÐ·Ð¾ÑÐºÐ°Ð·Ð½Ð¾Ð¹ ÑÐ°Ð±Ð¾ÑÑ ÑÐ¸ÑÑÐµÐ¼Ñ ÑÐ°ÑÑÑÐ¸ÑÑÐ²Ð°ÐµÑÑÑ Ñ Ð¿ÑÐ¸Ð¼ÐµÐ½ÐµÐ½Ð¸ÐµÐ¼ ÑÑÐ½ÐºÑÐ¸Ð¸ Ð¿Ð»Ð¾ÑÐ½Ð¾ÑÑÐ¸ Ð¾ÑÐºÐ°Ð·Ð¾Ð², ÑÑÐ½ÐºÑÐ¸Ð¸ Ð¸Ð½ÑÐµÐ½ÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ Ð¾Ð¿Ð°ÑÐ½Ð¾ÑÑÐ¸, Ð¾Ð±ÑÐµÐ¹ ÑÐ¾ÑÐ¼ÑÐ»Ñ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸, Ð±Ð»Ð¾Ðº-ÑÑÐµÐ¼Ñ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð¸ Ñ Ð¿Ð¾Ð¼Ð¾ÑÑÑ Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ñ SAPHIRE Ð¿ÑÑÐµÐ¼ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ñ Ð¾ÑÐ½Ð¾Ð²Ð½ÑÑ ÑÐ¾Ð±ÑÑÐ¸Ð¹ Ð¸ Ð¿Ð¾ÑÑÑÐ¾ÐµÐ½Ð¸Ñ Ð´ÐµÑÐµÐ²Ð° Ð¾ÑÐºÐ°Ð·Ð¾Ð². Ð ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ Ð¿ÑÐ¾Ð²ÐµÐ´ÐµÐ½Ð½Ð¾Ð³Ð¾ Ð¸ÑÑÐ»ÐµÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ Ð¼Ñ Ð¿Ð¾Ð½ÑÐ»Ð¸ ÐºÐ°Ðº Ð¿ÑÐ¸Ð¼ÐµÐ½ÑÑÑ ÑÐ¾ÑÐ¼ÑÐ»Ñ Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð½Ð° ÐÐ­Ð¡, Ð¿Ð°ÑÐ°Ð»Ð»ÐµÐ»ÑÐ½Ð¾Ðµ Ð¾Ð±ÑÐµÐ´Ð¸Ð½ÐµÐ½Ð¸Ðµ Ð±Ð»Ð¾ÐºÐ°/ÑÐ¸ÑÑÐµÐ¼Ñ/Ð¾Ð±Ð¾ÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÑÐ²Ð»ÑÐµÑÑÑ Ð±Ð¾Ð»ÐµÐµ Ð½Ð°Ð´ÐµÐ¶Ð½ÑÐ¼, Ð° ÑÐ¸ÑÑÐµÐ¼Ð° Ð¼ÐµÐ½ÐµÐµ Ð½Ð°Ð´ÐµÐ¶Ð½Ð°, ÐºÐ¾Ð³Ð´Ð° ÑÐ¸ÑÑÐµÐ¼Ð° ÑÐ°Ð±Ð¾ÑÐ°ÐµÑ Ñ Ð´Ð»Ð¸ÑÐµÐ»ÑÐ½ÑÐ¼ Ð²ÑÐµÐ¼ÐµÐ½ÐµÐ¼ Ð²ÑÐ¿Ð¾Ð»Ð½ÐµÐ½Ð¸Ñ Ð·Ð°Ð´Ð°Ð½Ð¸Ñ. ÐÐ¾Ð»ÐµÐµ ÑÐ¾Ð³Ð¾, Ð´Ð»Ñ ÑÑÐ½ÐºÑÐ¸Ð¸ ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½ÑÐ° Ð½Ð°Ð´ÐµÐ¶Ð½Ð¾ÑÑÐ¸ Ð»Ð°Ð±Ð¾ÑÐ°ÑÐ¾ÑÐ½Ð¾Ð³Ð¾ Ð¾Ð±Ð¾ÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ Ð·Ð½Ð°ÑÐµÐ½Ð¸Ñ ÑÐ°ÑÑÐ¼Ð°ÑÑÐ¸Ð²Ð°ÑÑÑÑ Ð² ÐºÐ¾Ð½ÑÐµÑÐ²Ð°ÑÐ¸Ð²Ð½Ð¾Ð¼ Ð¿Ð¾Ð´ÑÐ¾Ð´Ðµ.
description: PSA is a fundamental part of nuclear reactor safety from design to decommissioning. Its importance was first realized when the Three Mile Island Unit-2 accident occurred. Since the Fukushima Daiichi accident occurred, it is understood that nuclear safety analysis is important for safe operation. In this study, safety and reliability analysis performed for the laboratory set-up where in research center of Obninsk Institute of Nuclear Power Engineering of MEPhI at Obninsk, Russia. The laboratory is a design for Research Reactor Model, and it claims to understand ensuring reliability and safety by PSA for equipment of NPP. Reliability and probability of system working without failure are calculated by applying failure density function, hazard rate function, general reliability formula, reliability block diagram and performing SAPHIRE software by defining basic events and building a fault tree. Following the result of this study as understanding how to apply reliability formulas in NPP, parallel networking of unit/system/equipment is more reliable, and system is less reliable when the system operates with long mission time. Moreover, for the laboratory equipment reliability rate function, the values are considered in a conservative approach.