Published 1979 | Version v1
Journal article Metadata-only

Numerical simulation of transient conditions in main PWR plant circuits. Comparison of model with test data

Creators

  • 1. Electricite de France, 92 - Courbevoie. Service Etudes et Projets Thermiques et Nucleaires

Description

Numerical models simulating general operation of PWR equipment have been developed for dimensioning normal and emergency boiler water feed, steam diversion and other major systems, and for designing main governing and safety systems. Validity of the models was confirmed when they were used for preparation of commissioning tests and test data interpretation at Tihange and Fessenheim PWR plants

Abstract (French)

Des modeles numeriques de simulation du fonctionnement general des tranches PWR ont ete mis au point pour le dimensionnement de systemes importants tels que l'alimentation en eau normale et de secours de la chaudiere ou le contournement vapeur ainsi que pour la conception des chaines de regulation principales et de protection. L'utilisation de ces memes modeles lors de la preparation et de l'interpretation des essais de demarrage des centrales PWR de Tihange et de Fessenheim a permis leur validation

Additional details

Additional titles

Original title (French)
Simulation numerique des regimes transitoires dans les circuits principaux des tranches nucleaires PWR. Comparaison entre modeles et essais

Publishing Information

Journal Title
Houille Blanche
Journal Volume
34
Journal Issue
2-3
Series
Houille Blanche.
Journal Page Range
129-134
ISSN
0018-6368

Conference

Title
some present problems of hydraulic circuits.
Acronym
Session of the Societe Hydrotechnique de France
Dates
15 - 16 Nov 1978.
Place
Paris, France.

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
11522899
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPARATIVE EVALUATIONS; EXPERIMENTAL DATA; FUNCTIONAL MODELS; GRAPHS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR START-UP; SECONDARY COOLANT CIRCUITS; SIMULATION; THEORETICAL DATA; TRANSIENTS
Descriptors DEC
COOLING SYSTEMS; DATA; DATA FORMS; INFORMATION; NUMERICAL DATA; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS