Published December 2005 | Version v1
Journal article Metadata-only

System for passive heat removal in the new generation NPP

Creators

  • 1. FGUP Opytnoe Konstruktorskoe Byuro Mashinostroeniya im. I.I. Afrikantova, Nizhnij Novgorod (Russian Federation)

Description

Below is a brief description of mix, purpose and operation conditions of a system for passive heat removal (SPHR) of high capacity NPPs and a brief description of their models for bench tests. Paper presents the results of both theoretical and experimental studies of mechanism of initiation of parametric oscillations revealed during the mentioned calculations and experiments. One introduces a control algorithm and a facility to implement it ensuring stability of the SPHR operation. Paper presents data of the mentioned calculations and experiments showing validity of the made decisions

Abstract (Russian)

Дано краткое описание состава, назначения и режимов работы системы пассивного отвода тепла (СПОТ) атомных электростанций большой мощности, а также их моделей для испытаний на стендах. Приведены результаты теоретических и экспериментальных исследований механизма возникновения параметрических колебаний, выявленных в расчетах и экспериментах. Предложены алгоритм управления и устройство для его реализации, обеспечивающие устойчивость работы СПОТ. Представлены данные расчетов и экспериментов, подтвердившие правильность принятых решений

Additional details

Additional titles

Original title (Russian)
Системы пассивного отвода тепла АЭС нового поколения

Publishing Information

Journal Title
Teploehnergetika
Journal Issue
no.12
Journal Page Range
p. 50-54
ISSN
0040-3636
CODEN
TPLOA5

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
38076857
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ALGORITHMS; COMPARATIVE EVALUATIONS; FLOWSHEETS; HEAT TRANSFER; NUCLEAR POWER PLANTS; PARAMETRIC ANALYSIS; PRESSURE CONTROL; PRESSURE RANGE MEGA PA 01-10; REACTOR COOLING SYSTEMS; REACTOR OPERATION; STABILITY; TESTING
Descriptors DEC
CONTROL; COOLING SYSTEMS; DIAGRAMS; ENERGY SYSTEMS; ENERGY TRANSFER; EVALUATION; INFORMATION; MATHEMATICAL LOGIC; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; PRESSURE RANGE; PRESSURE RANGE MEGA PA; REACTOR COMPONENTS; THERMAL POWER PLANTS

Optional Information

Notes
6 refs., 9 figs.