title: ÐÑÐ¾Ð±ÐµÐ½Ð½Ð¾ÑÑÐ¸ Ð½ÐµÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½Ð¾Ð³Ð¾ ÑÐ°ÑÑÑÑÐ½Ð¾Ð³Ð¾ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ¾Ð² Ð¿Ð¾ ÑÐ±ÑÐ¾ÑÑ Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð·Ð°ÑÐ¸ÑÑ Ð´Ð»Ñ ÑÐµÐ°ÐºÑÐ¾ÑÐ¾Ð² ÑÐ¸Ð¿Ð° ÐÐÐ­Ð -1000
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: Aspects of transient computational modeling of safety system scram for VVER-1000 reactors
Creators: name: ÐÐ¾Ð»Ð¾Ð²Ð°ÑÐ°, ÐÐµÐ½Ð¸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: 2025
Subjects: Ð²Ð¾Ð´Ð¾-Ð²Ð¾Ð´ÑÐ½Ð¾Ð¹ ÑÐ½ÐµÑÐ³ÐµÑÐ¸ÑÐµÑÐºÐ¸Ð¹ ÑÐµÐ°ÐºÑÐ¾Ñ
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modeling
neytronic physics calculation
nuclear reactor
reactor control and safety system
reactor safety system efficiency
sapphire
water-water energy reactor

description: ÐÐ°Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° Ð¿Ð¾ÑÐ²ÑÑÐµÐ½Ð° ÑÐ¾Ð·Ð´Ð°Ð½Ð¸Ñ Ð¼ÐµÑÐ¾Ð´Ð¸ÐºÐ¸ ÑÐ¾Ð¿Ð¾ÑÑÐ°Ð²Ð»ÐµÐ½Ð¸Ñ Ð¿ÑÐ¾ÐµÐºÑÐ½ÑÑ ÑÐ°ÑÑÑÑÐ¾Ð² Ð¸ ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐ¾Ð² ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½ÑÐ¾Ð² Ð¿Ð¾ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÐµÐ½Ð¸Ñ Ð²ÐµÑÐ° Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð·Ð°ÑÐ¸ÑÑ. Ð Ð¿ÑÐ¾ÑÐµÑÑÐµ ÑÐ°Ð±Ð¾ÑÑ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²ÑÐ²Ð°ÐµÑÑÑ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·Ð¾Ð²Ð°Ð½Ð¸Ðµ Ð² ÑÐ°ÑÑÑÑÐ½Ð¾Ð¹ Ð¼Ð¾Ð´ÐµÐ»Ð¸ Ð¾Ð¿ÑÐµÐ´ÐµÐ»ÑÐ½Ð½ÑÑ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ñ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÐ¾Ð² Ð¸ ÑÐ°ÑÐ°ÐºÑÐµÑÐ¸ÑÑÐ¸Ðº, Ð¿Ð¾Ð·Ð²Ð¾Ð»ÑÑÑÐ¸Ñ Ð½Ð°Ð¸Ð±Ð¾Ð»ÐµÐµ ÑÐ¾ÑÐ½Ð¾ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°ÑÑ ÑÐºÑÐ¿ÐµÑÐ¸Ð¼ÐµÐ½Ñ, Ð²Ð²Ð¾Ð´Ð¸ÑÑÑ ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½Ñ ÐºÐ¾ÑÑÐµÐºÑÐ¸Ð¸ Ð´Ð»Ñ ÑÐ°ÑÑÑÑÐ¾Ð² ÑÐµÐ°ÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸ Ð¸ Ð¿ÑÐ¾Ð¸Ð·Ð²Ð¾Ð´ÑÑÑÑ ÑÐ°ÑÑÑÑÑ Ñ ÑÐµÐ»ÑÑ Ð¿Ð¾Ð¸ÑÐºÐ° Ð½Ð°Ð¸Ð±Ð¾Ð»ÐµÐµ ÑÑÑÐµÐºÑÐ¸Ð²Ð½Ð¾Ð³Ð¾ Ð¾ÑÐ³Ð°Ð½Ð° ÑÐµÐ³ÑÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ. Ð ÑÐ¾Ð´Ðµ ÑÐ°ÑÑÑÑÐ½Ð¾Ð³Ð¾ Ð¼Ð¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ñ Ð¸ÑÐ¿Ð¾Ð»ÑÐ·ÑÐµÑÑÑ Ð¿ÑÐ¾Ð³ÑÐ°Ð¼Ð¼Ð½ÑÐ¹ ÐºÐ¾Ð¼Ð¿Ð»ÐµÐºÑ Ð¡ÐÐÐ¤ÐÐ _95&amp;RC_ÐÐÐ­Ð . Ð ÑÐµÐ·ÑÐ»ÑÑÐ°ÑÐµ ÑÐ°Ð±Ð¾ÑÑ ÑÐ¾Ð·Ð´Ð°ÑÑÑÑ Ð¼ÐµÑÐ¾Ð´Ð¸ÐºÐ° ÑÐ¾Ð¿Ð¾ÑÑÐ°Ð²Ð»ÐµÐ½Ð¸Ñ Ð´Ð»Ñ Ð½ÐµÑÑÐ°ÑÐ¸Ð¾Ð½Ð°ÑÐ½ÑÑ ÑÐ°ÑÑÑÑÐ¾Ð² ÑÐ±ÑÐ¾ÑÐ° Ð°Ð²Ð°ÑÐ¸Ð¹Ð½Ð¾Ð¹ Ð·Ð°ÑÐ¸ÑÑ ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÐÐÐ­Ð -1000 Ð¸ Ð¿ÑÐ¾ÐµÐºÑÐ½ÑÑ ÑÐ°ÑÑÑÑÐ¾Ð², Ð²ÑÐ¿Ð¾Ð»Ð½ÑÑÑÑÑ Ð·Ð°Ð´Ð°ÑÐ¸ Ð¿Ð¾ Ð²ÑÐ±Ð¾ÑÑ Ð½ÐµÐ¹ÑÑÐ¾Ð½Ð½Ð¾-ÑÐ¸Ð·Ð¸ÑÐµÑÐºÐ¸Ñ Ð¿Ð°ÑÐ°Ð¼ÐµÑÑÐ¾Ð² Ð¸ Ð¾Ð±Ð¾ÑÐ½Ð¾Ð²Ð°Ð½Ð¸Ð¸ Ð²Ð²Ð¾Ð´Ð° ÐºÐ¾ÑÑÐµÐºÑÐ¸ÑÑÑÑÐµÐ³Ð¾ ÐºÐ¾ÑÑÑÐ¸ÑÐ¸ÐµÐ½ÑÐ° Ñ ÑÐµÐ»ÑÑ ÑÐ°ÑÑÑÑÐ° Ð¸ÑÑÐ¸Ð½Ð½ÑÑ Ð²ÐµÐ»Ð¸ÑÐ¸Ð½ ÑÐµÐ°ÐºÑÐ¸Ð²Ð½Ð¾ÑÑÐ¸.
description: The given work is devoted to project calculation and results comparison methodology creation for transient reactor scram modeling. In the process of work, the possibility of use the definite neutronic physical parameters is proven, enable to modelling scram experiments more accurately, introducing correction coefficient for reactivity calculation and identification the most effective control rod. During the computational modeling, the SAPFIR_95&amp;RC_VVER software package is used. As a result of work the comparison methodology for transient calculation of scram for reactor VVER-1000 and project calculation is created, the task of definite neutronic physical parameters choice and validation introducing correction coefficient for reactivity is accomplished.